Last edited by Fenrizahn
Friday, April 24, 2020 | History

4 edition of Application of RELAP5/MOD3.2 to the loss-of-residual-heat-removal event under shutdown condition found in the catalog.

Application of RELAP5/MOD3.2 to the loss-of-residual-heat-removal event under shutdown condition

Application of RELAP5/MOD3.2 to the loss-of-residual-heat-removal event under shutdown condition

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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:
  • Nuclear power plants -- Accidents -- Data processing,
  • Thermal analysis -- Mathematical models,
  • Water cooled reactors -- Loss of coolant

  • Edition Notes

    Statementprepared by K.W. Seul, Y.S. Bang, H.J. Kim
    SeriesInternational agreement report -- NUREG/IA-0182
    ContributionsBang, Y. S., Kim, H. J., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, Hanʾguk Wŏnjaryŏk Anjŏn Kisurwŏn
    The Physical Object
    FormatMicroform
    Paginationxiii, 53 p.
    Number of Pages53
    ID Numbers
    Open LibraryOL13627233M
    OCLC/WorldCa45081409

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Application of RELAP5/MOD3.2 to the loss-of-residual-heat-removal event under shutdown condition Download PDF EPUB FB2

Application of RELAP5/MOD to the Loss-of-Residual-Heat-Removal Event Under Shutdown Condition (NUREG/IA) On this page: Publication Information; Abstract; Download complete document. NUREG/IA (PDF MB) Publication Information. Date Published: April Prepared by: K.W.

Seul, Y.S. Bang, H.J. Kim, KINS. Korea Institute of. Application of RELAP5/MOD to the Loss-of-Residual-Heat-Removal Event Under Shutdown Condition Prepared by K.W Seul, Y.S. Bang, H.J. Kim, KINS Korea Institute of Nuclear Safety PO.

Box Yusung, TaejonKorea Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC April Get this from a library. Application of RELAP5/MOD to the loss-of-residual-heat-removal event under shutdown condition. [K W Seul; Y S Bang; H J Kim; U.S. Nuclear Regulatory Commission.

Office of Nuclear Regulatory Research.; Han'guk Wŏnjaryŏk Anjŏn Kisurwŏn.]. Get this from a library. Application of RELAP5/MOD to the loss-of-residual-heat-removal event under shutdown condition.

[K W Seul; Y S Bang; H J Kim; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research,]. Get this from a library. Assessment of RELAP5/MOD to the loss-of-residual-heat-removal event under shutdown condition. [K W Seul; Y S Bang; H J Kim; U.S.

Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.; Han'guk Wŏnjaryŏk Anjŏn Kisurwŏn.].

Therefore, this report describes the results of the quantification of the RELAP5/MOD model uncertainties related to the loss of residual heat removal (RHR) event during the PWR mid-loop operation. Based on the experimental literatures, the probability distributions of the model uncertainty were developed, which contributes to statistical Author: Toshihide Torige.

Application of RELAP5/MOD to the Loss-of-Residual-Heat-Removal Event Under Shutdown Condition NUREG/IA Analysis of the LOBI Experiment Test BT–56 Using the RELAP5/MOD Code. The loss of residual heat removal system (RHRS) at midloop operation is an important risk contributor at low power and shutdown conditions.

In this kind of transient the reflux-condensation can play an important role during the sequence to avoid the core by: Plant behavior following a loss-of-residual-heat-removal event under a shutdown conditions Application of RELAP5/ MOD to the Loss-of-heat-removal Event Under Shutdown Condition Flooding in the.

vapor in Residual Heat Removal (RHR) System in Modes 3/4 Loss-of-Coolant Accident (LOCA) Conditions. This concerns the Westinghouse standard 3-loops plant for which the RHR is the low pressure part of the Safety Injection (SI).

In some cases one or both RHR trains may become inoperable for Safety Injection (SI) : Kerim, Mathy. The transient following a loss-of-residual-heat-removal event during shutdown was analyzed to determine the containment closure time (CCT) to prevent uncontrolled release of.

Introduction. When a nuclear power plant is in shutdown conditions for refuelling, and to perform steam generator (SG) U-tubes and reactor coolant pump maintenance activities, the reactor coolant system water level is reduced to a height lower than the top of the hot leg pipe (Seo and Park, ).Under these conditions, it is said that the plant is in mid-loop by: 9.

As part of this work, the analyses of loss of residual heat removal (RHR) system under cold shutdown conditions for CPR are presented. For a pressurized water reactor (PWR), the RHR system is utilized to remove the decay heat when it is in cold shutdown operation for refueling or maintenance of the main components such as the steam Cited by: 2.

Application of RELAP5/MOD to the Loss-of-Residual-Heat-Removal Event Under Shutdown Condition Prepared by KW. Seul, Y.S. Bang, HJ. Kim, KINS Korea Institute of Nuclear Safety P.O. Box Yusung, TaejonKorea Office of Nudear Regulatory Research U.S. Nudear Regulatory Commission Washington, DC April Prepared as part of.

An analysis was performed using the RELAP5/MOD3 version code for a loss of residual heat removal event during midloop operation after reactor shutdown in. Accordingly, twelve typical cases were simulated to study the thermal-hydraulic behavior of loss of residual heat removal system for CPR under cold shutdown operation with RELAP5/MOD code.

Loss of residual heat removal system (RHRS) at midloop operation is one of the most significant core damage risk contributor at low power and shutdown conditions. During this kind of transients the reflux-condensation is one of the cooling mechanisms anticipated in the abnormal procedure of loss of RHRS at midloop by: 8.

The PIRT is developed for the loss of RHR event during mid-loop operation with mitigation measure of reflux cooling and gravity injection from RWST and important models of the RELAP5/MOD related to high ranked phenomena are identified. Verification matrix is also developed for the important by: 4.

RELAP5/ MOD computer code has been used to simulate the transient for WWER/V NPP model. A model of WWER based on Unit 6 of KNPP has been developed for the RELAP5/MOD code at the Institute for Nuclear Research and Nuclear Energy-Bulgarian Academy of Sciences (INRNE-BAS), by: 1.

RELAP5/MOD code capability for simulating transients under the established conditions. And also, to investigate if RELAP5/MOD could reproduce the physical phenomena involved in a LOCA transient in one of the RHR lines when the plant works at low power or shutdown conditions.

Under TCSEC, the ____ is the piece of the system that manages access controls—in other words, it mediates all access to objects by subjects. reference monitor Under the Biba model, the ____ property permits a subject to have read access to an object only if the security level of the subject is either lower or equal to the level of the object.

loss of residual heat removal in mid-loop operation (during shutdown conditions). These issues were investigated by means of thermal-hydraulic experiments that will be conducted at the Primarkreislauf-Versuchsanlage (primary coolant loop test facility) PKL. This facility is owned and operated by AREVA NP and is situated in Erlangen, Germany.

Analysis was performed for a large-break loss-of-coolant accident (LOCA) in the APR (Advanced Power Reactor MWe) with the thermal-hydraulic analysis code RELAP5/ MOD and the severe accident analysis code MAAP The two codes predicted different sequences for essentially the same initiating by: 2.

Get this from a library. Assessment of RELAP5/MOD with the LSTF experiment simulating a loss of residual heat removal event during mid-loop operation. [K W Seul; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research,].

Assessment of RELAP5/MOD with the LSTF experiment simulating a loss of residual heat removal event during mid-loop operation (OCoLC) Material Type: Government publication, National government publication: Document Type: Book: All Authors / Contributors: K W Seul; U.S.

Nuclear Regulatory Commission. Office of Nuclear Regulatory. Start studying UNIT 31 GAS HEAT NOTE BOOK QUESTIONS Learn vocabulary, terms, and more with flashcards, games, and other study tools. Plant Behavior Following a Loss-of-Residual-Heat-Removal Event Under a Shutdown Condition Kwang Won Seul, Young Seok Bang, Hho Jung Kim Nuclear Technology / Volume / Number 3 / June / Pages 3 Thermal runaway during blocking I Application Note 5SYA 1 Introduction The recent development of very high-voltage IGBT modules has lead to increased values of dissipated power during off-state, due to their higher blocking voltages, even if the leakage currents remain at similar levels as devices with lower blocking Size: KB.

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