Simulation of steam generator plugging tubes in a PWR to analyze the operating impact

被引:5
|
作者
Pla, Patricia [1 ]
Reventos, Francesc [2 ]
Ramos, Manuel Martin [3 ]
Sol, Ismael [4 ]
Strucic, Miodrag [1 ]
机构
[1] European Commiss, Joint Res Ctr, Inst Energy & Transport, Nucl Reactor Safety Assessment Unit, Westerduinweg 1, NL-1755 Petten, Netherlands
[2] Tech Univ Catalonia UPC, Barcelona, Spain
[3] European Commiss, Joint Res Ctr, Policy Support Coordinat, Nucl Safety & Secur Coordinat Unit, Brussels, Belgium
[4] Asociac Nucl Asco Vandellos II ANAV, Tarragona, Spain
关键词
NPP;
D O I
10.1016/j.nucengdes.2016.05.002
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A number of nuclear power plants (NPPs) with pressurized water reactors (PWR) in the world have replaced their steam generators (SG) due to degradation of the SG tubes caused by different problems. Several methods were attempted to correct the defects of the tubes, but eventually the only permanent solution was to plug them. The consequences of plugging the tubes are the decrease of heat transfer surface, the reduction of the flow area and subsequent reduction of the primary system mass flow and for a fraction of plugged tubes higher than a given value, the reduction of reactor output and economic losses. The objective of this paper is to analyze whether steam generator tube plugging has an impact in the effectiveness of accident management actions. An analysis with Relap5 Mod 3.3 patch03 for the Spanish reactor Asc6-2, a 3-loop 2940.6 MWth Westinghouse PWR, in which plugging of steam generator tubes are simulated, is presented in order to find the limit for the adequate operation of the plant. Several steady state calculations were performed with different fractions of plugged SG tubes, by modeling the reduction of the primary to secondary heat transfer surface and the reduction of the primary coolant mass flow area in the tubes as well. The results of the analysis yield that plugging 12% of the SG tubes is around the limit for optimal reactor operation. To complete the study two events, in which the steam generators are used to cooldown the plant, were simulated to find out if the plugging of SGs tubes could influence the efficiency of the operator actions described in the emergency operating procedures (EOPs) to handle this kind of events. The selected events have been the rupture of one tube of a SG (SGTR) and a small break LOCA (SBLOCA). Two transient cases with no plugging at all (0%) and 12% SG tube plugging were performed. The actions of the corresponding EOPs for SG tube rupture and SBLOCA were coded in the input deck. The results show no significant impact on operator actions. (C) 2016 Elsevier B.V. All rights reserved.
引用
收藏
页码:132 / 145
页数:14
相关论文
共 50 条
  • [1] ANALYSIS OF STEAM GENERATOR TUBE PLUGGING IN A PWR. INFLUENCE IN THE EMERGENCY OPERATING PROCEDURES
    Pla, Patricia
    Reventos, Francesc
    Martin Ramos, Manuel
    Sol, Ismael
    [J]. 22ND INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2013), 2013,
  • [2] THE INTEGRITY OF STEAM-GENERATOR TUBES AND PLUGGING ASSESSMENT
    AZODI, D
    SCHULZ, H
    ARENZ, R
    [J]. RES MECHANICA, 1990, 31 (01): : 61 - 75
  • [3] NON-CONDENSABLE GAS PLUGGING AND MIXING BEHAVIOR IN PWR STEAM GENERATOR TUBES DURING REFLUX CONDENSATION
    Janasz, Filip
    Prasser, Horst-Michael
    Suckow, Detlef
    Szogradi, Marton
    [J]. PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 6B, 2018,
  • [4] DENTING OF STEAM-GENERATOR TUBES IN PWR PLANTS
    VAIA, AR
    ECONOMY, G
    WOOTTEN, MJ
    ASPDEN, RG
    [J]. MATERIALS PERFORMANCE, 1980, 19 (02) : 9 - 24
  • [5] CFD simulation and flow-induced vibration evaluation of PWR steam generator U tubes
    Xiong Guangming
    Wang Yipeng
    Long Teng
    Guo Kai
    Tan Wei
    [J]. PROGRESS IN NUCLEAR ENERGY, 2021, 141
  • [6] DUCTILE FRACTURE SIMULATION OF A PIPE OF STEAM GENERATOR IN PWR
    Miyajima, Yuuki
    Kikuchi, Masanori
    Takahashi, Akiyuki
    [J]. PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2013, VOL 1A: CODES AND STANDARDS, 2014,
  • [7] MANAGEMENT OF PWR STEAM GENERATOR TUBE PLUGGING AND PRIMARY FLOW-RATE PREDICTIONS
    Brunin, Olivier
    [J]. PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE (PVP-2011), VOL 7, 2012, : 193 - 200
  • [8] Simulation of Flow Conditions in the Inlet Plenum of a PWR Steam Generator
    Kamenik, Blaz
    Tekavcic, Matej
    Marn, Jure
    Klienak, Ivo
    [J]. 27TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE (NENE 2018), 2018,
  • [9] Crack profiles identification of steam generator tubes in PWR plants using database
    Kojima, F
    Okajima, N
    [J]. ELECTROMAGNETIC NONDESTRUCTIVE EVALUATION (V), 2001, 21 : 97 - 104
  • [10] Effect of shot peening on primary water stress corrosion cracking of Alloy 600 steam generator tubes in an operating PWR plant
    Hur, DH
    Choi, MS
    Lee, DH
    Song, MH
    Kim, SJ
    Han, JH
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2004, 227 (02) : 155 - 160