CONCEPTUAL PLANT LAYOUT OF THE CANADIAN GENERATION IV SUPERCRITICAL WATER-COOLED REACTOR

被引:8
|
作者
Gaudet, M. [1 ]
Yetisir, M. [1 ]
Sartipi, A. [1 ]
机构
[1] Canadian Nucl Labs, Chalk River, ON K0J 1J0, Canada
关键词
Plant layout; plant design; reactor building; nuclear steam supply; Canadian supercritical water reactor;
D O I
10.12943/CNR.2016.00021
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
Canada is developing a 1200 MWe supercritical water-cooled reactor (SCWR), which has evolved from the well-established pressure-tube type CANDU (R)(1) reactor. This SCWR reactor concept, which is often referred to as the Canadian SCWR, uses supercritical water as a coolant, has a low-pressure heavy water moderator, and a direct cycle for power production. The reactor concept incorporates advanced safety features, such as passive emergency core cooling, long-term decay heat rejection to the environment, and fuel melt prevention via passive moderator cooling. To support these features, major systems and major components are identified and laid out inside the reactor buildings. The Canadian SCWR uses 2 nested reactor buildings for 2 separate functions: (i) a leak-tight containment building to house all safety-related systems and (ii) a shield building to protect critical components against external threats, such as airplane crashes, missile attacks, tornados, and flooding. Two redundant and independent passive safety systems are employed for a significant safety improvement over existing nuclear power plants. In passive safety systems, to provide sufficient driving force for naturally circulated coolant as well as to provide gravity head for a gravity-driven core flooding function, the Canadian SCWR reactor relies on elevation differences between the reactor core and the safety system components. These elevation differences, the required cooling pool volumes, and the optimum layout of safety-related piping are major factors influencing the containment design. As a defence-in-depth, the containment building and safety systems provide successive barriers to the unplanned release of radioactive materials, while providing a path for heat flow to the ultimate heat sink, the atmosphere. Access to the reactor core for refuelling is from the top of the reactor, with water used as shielding during the refuelling operations. The accessibility to the reactor and protection of the environment are additional factors influencing the plant design. This paper describes the physical implementation of the major systems of the Canadian SCWR within the reactor buildings and the position of major plant services relative to the reactor buildings.
引用
收藏
页码:203 / 219
页数:17
相关论文
共 50 条
  • [1] MECHANICAL ASPECTS OF THE CANADIAN GENERATION IV SUPERCRITICAL WATER-COOLED PRESSURE TUBE REACTOR
    Yetisir, M.
    Gaudet, M.
    Martin, D.
    [J]. PROCEEDINGS OF THE 20TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING AND THE ASME 2012 POWER CONFERENCE - 2012, VOL 2, 2012, : 725 - 730
  • [2] Fuel Assembly Concept of the Canadian Supercritical Water-Cooled Reactor
    Yetisir, Metin
    Hamilton, Holly
    Xu, Rui
    Gaudet, Michel
    Rhodes, David
    King, Mitch
    Andrew, Kittmer
    Benson, Ben
    [J]. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2018, 4 (01):
  • [3] Construction of the Dynamic Model and Control System for the Canadian Supercritical Water-Cooled Reactor Power Plant
    Han, Huirui
    Zhang, Chao
    [J]. NUCLEAR TECHNOLOGY, 2024, 210 (05) : 836 - 849
  • [4] Conceptual Design of Supercritical Water-cooled Reactor CSR150
    Ning, Zhonghao
    Wang, Lianjie
    Lu, Di
    Xia, Bangyang
    Huang, Yanping
    Chen, Xing
    [J]. Hedongli Gongcheng/Nuclear Power Engineering, 2023, 44 : 9 - 13
  • [5] Various Design Aspects of the Canadian Supercritical Water-Cooled Reactor Core
    Yetisir, Metin
    Xu, Rui
    Gaudet, Michel
    Movassat, Mohammad
    Hamilton, Holly
    Nimrouzi, Mohammedhossein
    Goldak, John A.
    [J]. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2016, 2 (01):
  • [6] Nuclear data sensitivity and uncertainty for the Canadian supercritical water-cooled reactor
    Blomeley, L.
    Pencer, J.
    Hyland, B.
    Adams, F. P.
    [J]. ANNALS OF NUCLEAR ENERGY, 2014, 63 : 587 - 593
  • [7] Materials Selection for the Canadian Supercritical Water-Cooled Nuclear Reactor Concept
    Li, Jian
    [J]. JOM, 2016, 68 (02) : 452 - 453
  • [8] DEVELOPMENT OF A HYDROGEN MANAGEMENT CONCEPT FOR THE CANADIAN SUPERCRITICAL WATER-COOLED REACTOR
    Gardner, Lee Brian
    Ryland, Don K.
    Suppiah, Sam
    [J]. CNL NUCLEAR REVIEW, 2019, 8 (01) : 1 - 8
  • [9] CANADIAN SUPERCRITICAL WATER-COOLED REACTOR CORE CONCEPT AND SAFETY FEATURES
    Yetisir, Metin
    Gaudet, Michel
    Pencer, Jeremy
    McDonald, Michael
    Rhodes, David
    Hamilton, Holly
    Leung, Laurence
    [J]. CNL NUCLEAR REVIEW, 2016, 5 (02) : 189 - 202
  • [10] Materials Selection for the Canadian Supercritical Water-Cooled Nuclear Reactor Concept
    Jian Li
    [J]. JOM, 2016, 68 : 452 - 453