Artificial Neural Network modelling of in-reactor diametral creep of Zr2.5%Nb pressure tubes at Indian PHWRs

被引：0
|
作者：
Sarkar, A. [1 ]
Sinha, S.K. [2 ]
Chakravartty, J.K. [1 ]
Sinha, R.K. [3 ]
机构：
[1] Materials Group, Bhabha Atomic Research Centre, Mumbai 400085, India
[2] Reactor Engineering Division, Bhabha Atomic Research Centre, Mumbai 400085, India
[3] Department of Atomic Energy, Anushakti Bhavan, Mumbai 400001, India
来源：
Annals of Nuclear Energy | 2014年 / 69卷
关键词：
549.3; Others; including Bismuth; Boron; Cadmium; Cobalt; Mercury; Niobium; Selenium; Silicon; Tellurium and Zirconium - 619.1 Pipe; Piping and Pipelines - 621.1 Fission Reactors - 706.1 Electric Power Systems - 804 Chemical Products Generally - 951 Materials Science;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
28
引用
收藏
页码：246 / 251
相关论文
共 33 条
  • [21] A HIGH-TEMPERATURE CREEP MODEL FOR ZR-2.5 WT-PERCENT NB PRESSURE TUBES
    SHEWFELT, RSW
    LYALL, LW
    GODIN, DP
    JOURNAL OF NUCLEAR MATERIALS, 1984, 125 (02) : 228 - 235
  • [22] Irradiation-induced creep of the Zr-2.5% Nb - A material for tubes of fuel channels of an RBMK-1000 reactor
    Averin, SA
    Sinel'nikov, LP
    Panchenko, VL
    Sagaradze, VV
    PHYSICS OF METALS AND METALLOGRAPHY, 2002, 94 (04): : 397 - 401
  • [23] Numerical simulation of high-temperature creep deformation in Zr-2.5%Nb pressure tubes of CANDU reactors
    Corzo, Santiago F.
    Ramajo, Damian E.
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2020, 179
  • [24] QUANTITATIVE CHARACTERIZATION OF HYDRIDE SPACING FOR COHESIVE ZONE MODELLING OF FRACTURE TOUGHNESS IN ZR-2.5NB PRESSURE TUBES
    Liu, Cheng
    Gutkin, Leonid
    Scarth, Douglas
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2016, VOL 1A, 2017,
  • [25] Selective extraction of niobium from Zr-Nb alloy: A way towards isolating long-lived 94Nb from discharged pressure tubes of Indian PHWRs
    Sarma, M.
    Ajith, N.
    Ghosh, M.
    Devi, P. S. Remya
    Ghosh, A.
    Swain, K. K.
    Patra, C. N.
    SEPARATION AND PURIFICATION TECHNOLOGY, 2025, 361
  • [26] Hydrogen transport in the oxide and hydrogen pickup by the metal during out- and in-reactor corrosion of Zr-2.5Nb pressure tube material
    Ramasubramanian, N
    Perovic, V
    Leger, M
    Kammenzind, B
    Kim, YS
    Elmoselhi, M
    ZIRCONIUM IN THE NUCLEAR INDUSTRY: TWELFTH INTERNATIONAL SYMPOSIUM, 2000, 1354 : 853 - 876
  • [27] Effect of manufacturing route on thermal creep behaviour of Zr-2.5Nb pressure tube alloy used in Indian PHWR
    Gopalan, Avinash
    Patel, Vivek
    Khandelwal, Harshit K.
    Devi, Y. Puspalatha
    Singh, R. N.
    JOURNAL OF NUCLEAR MATERIALS, 2022, 569
  • [28] Quantitative characterization of hydride spacing for cohesive-zone modelling of fracture toughness in Zr-2.5Nb pressure tubes
    Kinectrics Inc., Unit 2, 800 Kipling Avenue, Toronto
    ON
    M8Z 5G5, Canada
    ASME Pressure Vessels Piping Div. Publ. PVP,
  • [29] STRESS-DEPENDENCE OF IN-REACTOR CREEP RATE OF HEAT-TREATED ZR-2.5 WT PERCENT NB AND COLD-WORKED ZIRCALOY-2
    FIDLERIS, V
    JOURNAL OF NUCLEAR MATERIALS, 1970, 36 (03) : 343 - &
  • [30] Microstructural Studies of Zr-2.5Nb and Zircaloy-2 Pressure Tubes Irradiated in Indian Pressurized Heavy Water Reactors
    Srivastava, D.
    Banerjee, S.
    Neogy, S.
    Ramadasan, E.
    Anantharaman, S.
    Dey, G. K.
    Saibaba, N.
    ADVANCES IN MATERIALS AND PROCESSING: CHALLENGES AND OPPORTUNITIES, 2012, 585 : 56 - +
1234