Last edited by Dourisar
Sunday, July 12, 2020 | History

3 edition of RELAP5/MOD3.2 post test calculation of the PKL-experiment PKLIII-B4.3 found in the catalog.

RELAP5/MOD3.2 post test calculation of the PKL-experiment PKLIII-B4.3

RELAP5/MOD3.2 post test calculation of the PKL-experiment PKLIII-B4.3

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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 -- Control -- Computer simulation.,
  • Steam generating heavy water reactors -- Computer simulation.

  • Edition Notes

    Statementprepared by L. Karner.
    SeriesInternational agreement report -- NUREG/IA-0170.
    ContributionsU.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., Siemens Energierzeugung (Firm)
    The Physical Object
    FormatMicroform
    Paginationxvi, 68 p.
    Number of Pages68
    ID Numbers
    Open LibraryOL18138687M

    The RELAP5/MOD computer program has been used to analyze a series of tests investigating heat-transfer from a partly uncovered VVER core in the KS test facility at the Russian Research Center ''Kurchatov Institute'' (RRC-KI). The analysis documented represents VVER Standard Problem 4 in Joint Project 6, which is the investigation of Computer Code Validation for Transient Analysis of Author: A. Tentner, J. W. Ahrens.   Pharmacokinetic (PK) data (plasma drug concentrations) are routinely collected in early clinical studies. Several regulatory guidances describe the role of PK data in regulatory decisions. 1, 2 From an industry perspective, delineating PK characteristics in early phase clinical trials aids in the selection of the promising molecules and helps to make a go/no-go decision. 3, 4 However, the.

    RELAP5-MOD Assessment Studies Based on the PACTEL and PMK-2 Loss of Feed Water Tests Conference Paper (PDF Available) July with 59 Reads How we measure 'reads'. Makayla Stutts Experiment 2 Day Beaker 1 Beaker 2 Beaker 3 1 No Change No Change No Change 2 No Change Less white, thinned No Change 3 No Change Almost Clear, thinned more No Change 4 Less white, thinning some Very Clear, flappy like a jellyfish No Change 5 Even more less white, thinned more Very Clear, flappy like a jellyfish No Change 6 Same as day 6, no Change Very Clear, flappy like a.

    @article{osti_, title = {RELAP5/MOD Investigation of a VVER MCP Switching on Problem}, author = {Groudev, Pavlin and Pavlova, Malinka}, abstractNote = {This paper provides a discussion of various RELAP5 parameters calculated for the investigation of the nuclear power reactor parameter behavior in case of switching on one main coolant pump (MCP) when the other three . L Karner has written: 'RELAP5/MOD post test calculation of the PKL-experiment PKLIII-B' -- subject(s): Computer simulation, Control, Steam generating heavy water reactors, Pressurized water.


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RELAP5/MOD3.2 post test calculation of the PKL-experiment PKLIII-B4.3 Download PDF EPUB FB2

RELAP5/MOD Post Test Calculation of the PKL-Experiment PKLIII-B Prepared by L. Karner Siemens Energierzeugung (KWU) Freyerslebenstrasse 1 D Erlangen Germany Office of Nuclear Regulatory Research U.S.

Nuclear Regulatory Commission Washington, DC December Prepared as part of. NRC: RELAP5/MOD Post Test Calculation of the PKL-Experiment PKLIII-B (NUREG/IA) The Nuclear Regulatory Commission, protecting people and the environment.

Skip to Main Page ContentSkip to SearchSkip to Site Map NavigationSkip to Footer Links. Home. Open Library is an open, editable library catalog, building towards a web page for every book ever published.

RELAP5/MOD post test calculation of the PKL-experiment PKLIII-B by L. Karner,Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Supt. of Docs., U.S. G.P.O. [distributor edition, Microform in EnglishPages: RELAP5/MOD post test calculation of the PKL-experiment PKLIII-B (OCoLC) Material Type: Government publication, National government publication: Document Type: Book: All Authors / Contributors: L Karner; U.S.

Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.; Siemens Energierzeugung (Firm). RELAP5/MOD post test calculation of the PKL-experiment PKLIII-B (OCoLC) Material Type: Document, Government publication, National government publication, Internet resource: Document Type: Internet Resource, Computer File: All Authors / Contributors: L Karner; Siemens Energierzeugung (Firm),; U.S.

Nuclear Regulatory Commission. Division of Systems Analysis and. NUREG/IA International Agreement Report RELAP5/MOD Post Test Calculation of the PKL-Experiment PKLIII-B Prepared by L Kamer Siemens Energierzeugung (KWU) Freyerslcbenstrasse 1 D Erlangen Germany Office of Nuclear Regulatory Research U.S.

Nuclear Regulatory Commission Washington, DC December Prepared as part of. Get this from a library. RELAP5/MOD post test analysis and accuracy quantification of SPES test SP-SB [F D'Auria; M Frogheri; W Giannoti; U.S. Nuclear Regulatory Commission.

Office of Nuclear Regulatory Research,]. The Relap5/Mod [1] is based on a non-homogeneous, non-equilibrium set of six partial differential balance equations for the steam and the liquid phases. A non-condensable component in the steam phase and a non-volatile component (boron) in the liquid phase can be treated by the code.

RELAP5/MOD Assessment Using INSC SP-PSBV1. Conference Paper The accumulator injection was more effective in quenching the core in the test than in the INEEL calculation. This difference is. RELAP5/MOD post test analysis and accuracy quantification of Lobi test BL (OCoLC) Material Type: Government publication, National government publication: Document Type: Book: All Authors / Contributors: F D'Auria; M Frogheri; W Giannoti; U.S.

Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.; Università di Pisa. RELAP5/MOD model. This section describes the modeling assumptions and nodalization for the development of a RELAP5/MOD model for VVER, Unit 1 Rivne NPP (Borissenko et al., ).

The Baseline input deck for VVER/V Rivne Nuclear Power Plant Unit 1, is provided by National Taras Shevchenko University of by: 5. COVID Resources. Reliable information about the coronavirus (COVID) is available from the World Health Organization (current situation, international travel).Numerous and frequently-updated resource results are available from this ’s WebJunction has pulled together information and resources to assist library staff as they consider how to handle coronavirus.

The following sections of this report include a description of VVER power plant, description of the test being studied, a description of the RELAP5/MOD input model, results, and conclusions.

VVER Nuclear power plant description. The reference power plant design for this analysis is Unit 6 at the Kozloduy NPP by: 3. RELAP5/MOD Post Test Calculation of the PKL-Experiment PKLIII-B NUREG/IA Simulation of LOCA 6" and LOCA 2" Transients in the RHR of a PWR Under Low Power Conditions Using RELAP5/MOD Assessment of RELAP5/MOD using LOFT large break LOCA test, LP (SuDoc Y 3.N /) on *FREE* shipping on qualifying offers.

Assessment of RELAP5/MOD using LOFT large break LOCA test, LP (SuDoc Y 3.N /)Manufacturer: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission. A input deck of the Kozloduy Unit #4 has been developed for the systems thermal-hydraulics code RELAP5/MOD (Carlson et al., ).

The Relap5/MOD (Fletcher and Schultz, ) input model was developed at the Institute for Nuclear Research and Nuclear Energy. Data and information for modeling of these systems were obtained from Cited by: 7. In the current research, the RELAP5/MOD is assessed in its capability of predicting startup transients in a natural circulation test facility simulating a BWR-type SMR.

The RELAP5 simulations were compared to the experimental startup databases under two different power ramp rates, i.e., the fast startup and slow startup by: 6. Experiment no. 3 No-Load and Blocked Rotor Test on.

Three Phase Induction Motor. Aim of the Experiment: 1. To obtain the variation of no load power and current and blocked rotor power and current with changes in the applied voltage to the stator.

To determine the equivalent circuit parameters of an induction motor. No load test: THEORY:File Size: 81KB. Zope > Purdue Advanced Reactor Core Simulator > PARCS Code > Test Suite > By Calculation Mode > Coupled Mode Problems > Coupled Problems with RELAP5 > Coupled Problems with RELAP5 AER VVER Control Rod Ejction Problem at HZP ($ ERW).

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.

Chapter 4 Single Equilibrium Stages and Flash Cal-culations 1. The which applies to intensive vari-ables at equilibrium, determines the number of indepen-dent variables that can be speci–ed.

This rule can be extended to the more general determination of the de-grees of freedom (number of allowable speci–cations) forFile Size: KB.RELAP5/MOD sensitivity calculations of loss-of-feed water (LOFW) transient at Unit 6 of Kozloduy NPP.In this study, we performed post-test analysis for the LSTF test by using the RELAP5/MOD code (USNRC Nuclear Safety Analysis Division, ) to clarify the remaining subjects.

In the analysis, the core was modeled considering the cross-flow between different power rod bundles for better representation of multi-dimensional flow in the core Cited by: 2.