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Saturday, May 16, 2020 | History

4 edition of Development and validation of a transition boiling model for the RELAP5/MOD3 reflood simulation found in the catalog.

Development and validation of a transition boiling model for the RELAP5/MOD3 reflood simulation

Development and validation of a transition boiling model for the RELAP5/MOD3 reflood simulation

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Published by Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission in Washington, DC .
Written in English

    Subjects:
  • Heat -- Transmission -- Computer simulation,
  • Light water reactors -- Computer simulation,
  • Water cooled reactors -- Loss of coolant -- Computer simulation

  • Edition Notes

    Statementprepared by V.H. Sanchez-Espinoza ... [et al.]
    SeriesInternational agreement report -- NUREG/IA-0185
    ContributionsSanchez-Espinoza, V. H, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, Forschungszentrum Karlsruhe
    The Physical Object
    FormatMicroform
    Paginationxiii, 89 p.
    Number of Pages89
    ID Numbers
    Open LibraryOL15491072M
    OCLC/WorldCa52418575

    Free essays, homework help, flashcards, research papers, book reports, term papers, history, science, politics. Razširjeno - Uprava Republike Slovenije za jedrsko varnost REPUBLIKA SLOVENIJA MINISTRSTVO ZA KMETIJSTVO IN OKOLJE UPRAVA REPUBLIKE SLOVENIJE ZA JEDRSKO VARNOST Razširjeno poročilo o varstvu pred ionizirajočimi sevanji in jedrski varnosti v Republiki Sloveniji leta Razširjeno poročilo o varstvu pred ionizirajočimi sevanji in jedrski varnosti v Republiki Sloveniji leta Naslov.

    Chen transition boiling correlation database Separate-effects tests used in validation of EPRI drift flux model. The mission of the RELAP5/MOD3 development program was to develop a code version suitable for the analysis of all transients and postulated accidents in PWR systems, including both large- and small-break loss-of-coolant. ABSTRACTA thermal-hydraulic integral effect test facility, SMART-ITL, was constructed to examine the system performance of SMART, a MWt integral type reactor, and to provide data for validation of related thermal-hydraulic models in the system analysis codes. SMART is equipped with various passive systems such as a passive residual heat removal system (PRHRS), a passive safety injection Cited by: 2.

    USNRC - Free ebook download as PDF File .pdf), Text File .txt) or read book online for free. Volume 4 Models and Correlations. Assessment of RELAP5/MOD gamma with the LOFT L experiment simulating an anticipated transient without scram Responsibility prepared by J.K. Suh, Y.S. Bang, H.J. Kim.


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Development and validation of a transition boiling model for the RELAP5/MOD3 reflood simulation Download PDF EPUB FB2

The above assessments point out the need to improve the transition boiling model in R5M3. In order to take credit of the extensive validation of the original Chen model (Chen et al., ), it was considered desirable to extend that model to fit the range of conditions expected during hypothetical LOCA and degraded core accidents and to implement it in the R5M3 and the coupled SCDAP/RELAP5 Cited by: Get this from a library.

Development and validation of a transition boiling model for the RELAP5/MOD3 reflood simulation. [Victor Hugo Sanchez-Espinoza; U.S.

Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.; Forschungszentrum Karlsruhe.;]. Get this from a library. Development and validation of a transition boiling model for the RELAP5/MOD3 reflood simulation.

[V H Sanchez-Espinoza; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research,]. The original RELAP5/MOD code has a special model to consider the increase of film boiling or transition boiling HTCs at the point close to the top quench position.

The code uses a modified form of the Weismann correlation to estimate the transition boiling HTC to the liquid when the distance to the top quench front is not greater than by: 5.

Assessment of RELAP5/MOD Against Single Rod Reflooding Experiments N. Lymperea, N. Lymperea. Development and Validation of a Transition Boiling Model for RELAP5:MOD3 Reflood Simulation,” Nucl. Eng. Des., (3Cited by: 1. Assessment of RELAP5/MODNPA against an inadvertent closure of all three MSIV's in VANDELLOS-II Nuclear Power Plant / by: Llopis, C., et al.

Published: () Assessment and application of blackout transients at Asco nuclear power plant with RELAP5/MOD2 / by: Reventós, F. Improvement of the reflood model of RELAP5/MOD based on the assessments against FLECHT-SEASET tests Article in Nuclear Engineering and Design (4) April with 15 Reads.

Karlsruhe Sodium Laboratory (KASOLA) is focused on innovative energy technology, using liquid metals for efficient heat transfer and energy conversion. Beside the main KASOLA facility, which can.

RELAP5/MOD3 Subcooled Boiling Model Assessment Prepared by A. Devkin and A. Podosenov Nuclear Safety Institute Russian Research Centre "Kurchatov Institute" Kurchatov Square, 1Moscow Russia Ofice of Nuclear Regulatory Research U.S.

Nuclear Regulatory Commission Washington, DC ' "0 May Prepared as part ofCited by:   Reflooding of a hot damaged core following the start of a severe accident can lead to significant increases in the heating, melting, and oxidation of the core prior to the termination of the accident.

These effects have been observed in bundle heating and melting experiments terminated by the addition of water and are postulated to have had a major impact on the accident progression in the Author: J.K.

Hohorst, C.M. Allison. The SCDAP/RELAP5 code has been developed for best-estimate transient simulation of light water reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system and reactor core during severe accidents as well as large and small break loss-of-coolant accidents, operational transients such as.

Results show good agreement between experiments and RELAP5/MOD results. This research provides experimental data for evaluation of thermo hydraulic codes for nuclear research reactors, and veri es that RELAP5/MOD has a good capability to estimate the thermal hydraulic behavior of Author: M Taherzadeh, J Jafari, N Vosoughi, H Arabnezhad.

Modifications or control have been separately introduced on such models or correlations as fission product decay model, correlations for critical heat flux (CHF), post-CHF heat transfer correlations, logic of preventing from returning nucleate boiling and transition boiling heat transfer prior to reflood, discharge model, metal-water reaction Author: Bo Kuang, Lu Lu, Thomas K.

Liang. The potential for the RELAP5/MOD code was assessed for the loss of residual heat removal (RHR) event during the mid-loop operation. The predictability of major thermal hydraulic phenomena was evaluated for the long term transient.

The results of two typical cases, cold leg opening (CLO) case with water-filled steam generators (SGs) and. RELAP5/MOD code in simulating transients under Research Reactors operating conditions[1]. In this framework two Loss Of Flow Transient (LOFT) cases are considered.

The first case is LOFT with and without Scram and it is based upon a realistic hypothesis which takes into account the power feedback using the point kinetic approach. In the secondCited by: 5.

Full text of "Development of fission-products transport model in severe-accident scenarios for SCDAP/RELAPS" See other formats. Physical-Mathematical Model Development Derivation of the Fission Products-Transport Analytical Equations Recalling that the purpose of the model is to determine fission-products masses released to the containment, the problem can be seen as a mass transport problem, i.e., a mass conservation equation, with a convective term.

RELAP5/SCDAPSIM and MAAP4 are two widely used severe accident computer codes for the integral analysis of the core and the reactor pressure vessel behaviour following the core degradation. The objective of the paper is the comparison of code results obtained by application of different modelling options and the evaluation of influence of thermal hydraulic behaviour of the plant on core damage Cited by: 1.

RELAP5/MOD Analysis of the Reactor Coolant Pump Trip Event at NPP Krško for Different Transient Scenarios Sabina Markelj, Zdravko Rupnik, Iztok Čadež - Slovenia Detection System for Vibrational Spectroscopy of Hydrogen Molecules for Studies of Collision Processes in Fusion Edge Plasma.

August – Present GE-Hitachi Nuclear. Stability and Radiological Team. Senior Stability Engineer: Performing analyses of commercial boiling water nuclear reactors core reloads to establish the stability boundaries of the core design and to apply accepted stability solutions in accordance with regulations and customer requirements.

The most important strategies assumed were primary side depressurization and additional makeup water to reactor coolant system (RCS).

For simulations of long term SBO scenarios, including early stages of severe accident sequences, the best estimate RELAP5/MOD and the verified input model of Krško two-loop PWR were used. AbstractBottom reflooding is the third phase when a large-break loss-of-coolant accident occurs. Due to the complexity and importance, especially in a distinct narrow rectangular channel, various research methods can be utilized to understand the whole process.

Test facility is established to figure out the thermal-hydraulic behaviors during bottom reflooding, and the acquisition of accurate Cited by: 2.A Bayesian approach to treat expert-elicited probabilities in human reliability analysis model construction Podofillini L, Dang V N RELIABILITY ENGINEERING & SYSTEM SAFETY().

DOI: / A Long-Term Electricity Dispatch Model with the TIMES Framework Kannan Ramachandran, Turton Hal ENVIRONMENTAL MODELING & ASSESSM (). .