Modeling of pressurizer using APROS and TRACE thermal hydraulic codes

被引：0
|
作者：
机构：
来源：
VTT Tied Valt Tek Tutkimuskeskus | 2006年 / 2339卷 / 3-99期
关键词：
19;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
引用
收藏
相关论文
共 50 条
  • [21] EXPERIMENTAL STUDY OF THERMAL AND HYDRAULIC CHARACTERISTICS OF PRESSURIZER-TYPE HEATING CONTAINER DURING BLOWDOWN PROCESS
    Ke, Bingzheng
    Gao, Puzhen
    Wang, Bo
    Chen, Bowen
    Li, Ru
    Tian, Ruifeng
    Cheng, Kun
    Lu, Chuan
    PROCEEDINGS OF THE 2020 INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING (ICONE2020), VOL 3, 2020,
  • [22] Analysis of potential waterhammer at the Ignalina NPP using thermal-hydraulic and structural analysis codes
    Uspuras, E
    Kaliatka, A
    Dundulis, G
    NUCLEAR ENGINEERING AND DESIGN, 2001, 203 (01) : 1 - 12
  • [23] Benchmark calculations of pressurizer model for Maanshan nuclear power plant using TRACE code
    Cheng, Yi-Hsiang
    Wang, Jong-Rong
    Lin, Hao-Tzu
    Shih, Chunkuan
    NUCLEAR ENGINEERING AND DESIGN, 2009, 239 (11) : 2343 - 2348
  • [24] Prediction of Flow Regimes and Thermal Hydraulic Parameters in Two-Phase Natural Circulation by RELAP5 and TRACE Codes
    Viet-Anh Phung
    Kudinov, Pavel
    SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2015, 2015
  • [25] Analysis of the IAEA SPE-4 small-break LOCA experiment with RELAP5, TRACE and APROS system codes
    Varju, Tamas
    Aranyosy, Adam
    Orosz, Robert
    Holl, Viktor
    Hajas, Tamas
    Aszodi, Attila
    NUCLEAR ENGINEERING AND DESIGN, 2021, 377
  • [26] Improvement of the subcooled boiling model for thermal?hydraulic system codes
    Ha, Tae-Wook
    Yun, Byong-Jo
    Jeong, Jae Jun
    NUCLEAR ENGINEERING AND DESIGN, 2020, 364
  • [27] TRETA and TIZONA fast running thermal-hydraulic codes
    Izquierdo, J. M.
    Sanchez, M.
    Hortal, F. J.
    Melendez, E.
    Herrero, R.
    Queral, C.
    Exposito, A.
    Gonzalez, I.
    ANNALS OF NUCLEAR ENERGY, 2007, 34 (07) : 533 - 549
  • [28] Assessment of uncertainties of the models used in thermal–hydraulic computer codes
    Gricay A.S.
    Migrov Y.A.
    Thermal Engineering, 2015, 62 (9) : 656 - 662
  • [29] UNCERTAINTIES IN PREDICTIONS BY THERMAL-HYDRAULIC CODES: APPROACHES AND RESULTS
    Petruzzi, A.
    D'Auria, F.
    PROCEEDINGS OF THE ASME FLUIDS ENGINEERING DIVISION SUMMER CONFERENCE - 2010 - VOL 1, PTS A-C, 2010, : 1519 - 1531
  • [30] Sensitivity analysis of the IAEA SPE-2 small-break LOCA experiment with RELAP5, TRACE and APROS system codes
    Varju, Tamas
    Orosz, Robert
    Aranyosy, Adam
    Holl, Viktor
    Hajas, Tamas
    Aszodi, Attila
    NUCLEAR ENGINEERING AND DESIGN, 2022, 388
12345