Study of the beltline weld and base metal of WWER-440 first generation reactor pressure vessel

被引：0
|
作者：
J. Schuhknecht
U. Rindelhardt
H.-W. Viehrig
机构：
[1] Forschungszentrum Dresden-Rossendorf (FZD),
来源：
Strength of Materials | 2010年 / 42卷
关键词：
WWER-type reactors; reactor pressure vessel steel; weld metal; base metal; trepan; welding seam; fracture toughness; Master Curve; Charpy-V specimens;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
We present experimental results of the circumferential core weld SN0.1.4 and the base metal ring 0.3.1 of the reactor pressure vessel from the Unit 1 of the Greifswald WWER-440/230. The investigated trepans represent the irradiated–annealed– reirradiated (IAI) condition. The working program is focused on the characterization of the reactor pressure vessel steels through the reactor pressure vessel wall. The key part of the testing is aimed at the determination of the reference temperature T0 following the ASTM Test Standard E1921 to determine the fracture toughness in different thickness locations.
引用
收藏
页码：70 / 77
页数：7
相关论文
共 50 条
  • [1] STUDY OF THE BELTLINE WELD AND BASE METAL OF WWER-440 FIRST GENERATION REACTOR PRESSURE VESSEL
    Schuhknecht, J.
    Rindelhardt, U.
    Viehrig, H. -W.
    STRENGTH OF MATERIALS, 2010, 42 (01) : 70 - 77
  • [2] Investigation of the Beltline Welding Seam and Base Metal of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel
    Schuhknecht, Jan
    Viehrig, Hans-Werner
    Rindelhardt, Udo
    JOURNAL OF ENGINEERING FOR GAS TURBINES AND POWER-TRANSACTIONS OF THE ASME, 2011, 133 (05):
  • [3] INVESTIGATION OF THE BELTLINE WELDING SEAM AND BASE METAL OF THE GREIFSWALD WWER-440 UNIT 1 REACTOR PRESSURE VESSEL
    Schuhknecht, Jan
    Viehrig, Hans-Werner
    Rindelhardt, Udo
    ICONE 17: PROCEEDINGS OF THE 17TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 1, 2009, : 289 - 295
  • [4] Fracture mechanics characterisation of the WWER-440 reactor pressure vessel beltline welding seam
    Viehrig, Hans-Werner
    Schuhknecht, Jan
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2009, 86 (04) : 239 - 245
  • [5] Investigation of beltline welding seam of the greifswald WWER-440 unit 1 reactor pressure vessel
    Viehrig, Hans-Werner
    Schuhknecht, Jan
    Rindelhardt, Udo
    Weiss, Frank-Peter
    Journal of ASTM International, 2009, 6 (05):
  • [6] Impact of shield elements on the WWER-440 reactor pressure vessel activation
    Narkunas, Ernestas
    Poskas, Gintautas
    Smaizys, Arturas
    ANNALS OF NUCLEAR ENERGY, 2019, 130 : 394 - 401
  • [7] Microstructure Response of WWER-440 Reactor Pressure Vessel Weld Material After Irradiation and Annealing Treatment
    Zeman, A.
    Chernobaeva, A.
    Grafutin, V.
    Rogozhkin, S.
    Debarberis, L.
    Ballesteros, A.
    Erak, D.
    Nikitin, A.
    EFFECTS OF RADIATION ON NUCLEAR MATERIALS: 25TH VOLUME, 2013, 1547 : 85 - 108
  • [8] Prediction of irradiation embrittlement in WWER-440 reactor pressure vessel materials
    Brumovsky, M.
    Kytka, M.
    Debarberis, L.
    Gillemot, F.
    Kryukov, A.
    Valo, M.
    PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY, 2007, (06): : 72 - 77
  • [9] Flux effect analysis in WWER-440 reactor pressure vessel steels
    Kryukov, A.
    Blagoeva, D.
    Debarberis, L.
    JOURNAL OF NUCLEAR MATERIALS, 2013, 443 (1-3) : 171 - 175
  • [10] Numerical simulation of hydrogen diffusion in the pressure vessel wall of a WWER-440 reactor
    Toribio, J.
    Vergara, D.
    Lorenzo, M.
    2ND INTERNATIONAL CONFERENCE ON ENERGY MATERIALS AND APPLICATIONS (ICEMA2017), 2017, 222
12345