The preparation of segmenting the TRR reactor vessel internals with higher radiation

被引:0
|
作者
Cheng, Kuei-Jen [1 ]
Peng, Chen-Chzu [1 ]
Shen, Yu-Yu [1 ]
Lee, Hsueh-Yuan [1 ]
Chen, Peng-Yu [1 ]
机构
[1] Inst Nucl Energy Res, Taipei, Taiwan
关键词
Taiwan research reactor; Internals; Segmentation;
D O I
10.1016/j.ijpvp.2022.104635
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Based on the approved Taiwan Research Reactor (TRR) Decommissioning Plan, TRR decommissioning task must be finished before March 2029, and the reactor vessel should be fully dismantled before the end of 2028. However, Taiwan has no experience on dismantling a nuclear reactor vessel and lacks the associated containers and equipments, especially those used for handling the internals with higher radiation. To reach the goal of dismantling TRR reactor vessel in time, Institute of Nuclear Energy Research (INER) has made the dismantling strategy and developed the associated containers and equipments. Concerning the personnel safety, these internals with higher radiation will be segmented under the water. This makes the equipments and container used for segmenting these internals and storing the segmented parts are hard to be accessed from the commercial market directly and need to be developed in advance. To cope with these challenges, INER has designed the underwater disc saw and band saw equipments to segment these internals and developed INER-LRW-C2 low level radioactive waste container to store and transport those segmented parts. Currently, these equipments used for segmenting these internals are under mockup tests, and INER-LRW-C2 low level radioactive waste container has been granted the usage permit.The content of this article briefly introduces how INER prepares to face these challenges and what it has done. This includes the TRR reactor vessel dismantling strategy and segmentation plan of these internals with higher radiation, the development of INER-LRW-C2 low level radioactive waste container, and the designs of these major associated segmentation equipments.
引用
收藏
页数:10
相关论文
共 50 条
  • [31] Radiological characterization of the pressure vessel internals of the BNL high flux beam reactor
    Holden, NE
    Reciniello, RN
    Hu, FP
    HEALTH PHYSICS, 2004, 87 (02): : S25 - S30
  • [32] VVER-440 NPP REACTOR VESSEL AND REACTOR INTERNALS DESIGN REVIEW CALCULATION USING ASME BPVC
    Palfi, Tamas
    Palfi, Peter
    Ratkai, Sandor
    Dancso, Sandor
    ASME PRESSURE VESSELS AND PIPING CONFERENCE, VOL 7: OPERATIONS, APPLICATIONS AND COMPONENTS, 2010, : 489 - 493
  • [33] Use of MCNP for characterization of reactor vessel internals waste from decommissioned nuclear reactors
    Love, EF
    Pauley, KA
    Reid, BD
    PROCEEDINGS OF THE 1996 TOPICAL MEETING RADIATION PROTECTION & SHIELDING, VOLS 1 AND 2, 1996, 1-2 : 565 - 572
  • [34] MATERIALS AGING DEGRADATION OF REACTOR VESSEL INTERNALS PART I: THERMAL HYDRAULICS EVALUATION
    Liszkai, Tamas R.
    Yee, Norm S.
    Smotrel, Jim R.
    Demma, Anne
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, VOL 4, 2009, : 303 - 312
  • [35] Seismic analysis of the APR 1400 reactor vessel internals using the model reduction method
    Choi, Youngin
    Park, Jong-Beom
    Lee, Sang-Jeong
    Park, No-Cheol
    Park, Young-Pil
    Kim, Jin-Sung
    Roh, Woo-Jin
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2016, 53 (11) : 1701 - 1714
  • [36] Computational Methods and Representative Cases for Fluid–Structure Interaction in Nuclear Reactor Vessel and Internals
    Pascal Veber
    Fredrik Tornberg
    Afaque Shams
    Osman K. Siddiqui
    Arabian Journal for Science and Engineering, 2025, 50 (5) : 3591 - 3615
  • [37] Creating an element of the reactor vessel internals of the VVER by directed metal deposition (DMD) methods
    Shakirov, Ivan
    Kuznetsov, Pavel
    Bobyr, Vitaliy
    Zhukov, Anton
    Dub, Alexey
    Shchurenkova, Svetlana
    MATERIALS TODAY-PROCEEDINGS, 2021, 38 : 1946 - 1951
  • [38] THERMAL ANNEALING OF WWER-440 NUCLEAR REACTOR PRESSURE VESSEL INTERNALS MATERIAL
    Schnablova, Ivana
    Kopriva, Radim
    Bursik, Ondrej
    Rusnakova, Katerina
    Materna, Ales
    29TH INTERNATIONAL CONFERENCE ON METALLURGY AND MATERIALS (METAL 2020), 2020, : 416 - 421
  • [39] ANALYSES OF THERMAL ANNEALING INFLUENCE ON WWER 440 REACTOR PRESSURE VESSEL INTERNALS MATERIALS
    Petelova, Petra
    Eliasova, Ivana
    Kopriva, Radim
    Bursik, Ondrej
    Tonarova, Dana
    Materna, Ales
    28TH INTERNATIONAL CONFERENCE ON METALLURGY AND MATERIALS (METAL 2019), 2019, : 787 - 792
  • [40] LICENSING ASSESSMENT - ONE-PIECE REMOVAL OF SHIPPINGPORT REACTOR VESSEL, INTERNALS BY BARGE
    RAINISCH, R
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1982, 43 : 573 - 574