Application of an Independent Temporary Spent Fuel Storage Pool Cooling System for Decommissioning of Pressurized Water Reactor Kori Units 3 and 4

被引:1
|
作者
Mah, Wonjune [1 ]
Kim, Chang-Lak [1 ]
机构
[1] KEPCO Int Nucl Grad Sch, 658-91 Haemaji Ro, Ulsan 45014, South Korea
关键词
nuclear power plant; decommissioning; temporary spent fuel storage pool cooling system; temporary spent nuclear fuel storage; spent fuel pool island (SFPI);
D O I
10.3390/en16021009
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
The operating license of Kori units 3 and 4 are to be expired in 2024 and 2025. If the plants are decided to be decommissioned, the spent nuclear fuels in the spent fuel storage pool (SFP) have to be removed from the site. However, no proper storage facility is currently available in Korea. To overcome the difficulty, this study proposes application of an independent temporary SFP cooling system. It is expected to safely isolate the SFP from the plant. The case study conducted showed this concept is achievable and technically mature. Moreover, the installation cost per unit is USD 9.51 million obtained from an analogous estimating. This is much lower cost than the dry cask options. Then, system requirements and applicable design are developed. Maximum heat generation of unit 4 is estimated as 1.67 MW, through fuel characteristics categorizations and ORIGEN calculations. To remove the decay heat, installation of an indirect air-cooled method is selected by evaluating three cooling methods. The modification includes new heat exchanger, secondary cooling pumps, and chillers. Furthermore, two single failures are considered; cooling pump and normal power. This can be covered by two redundant trains and a back-up diesel generator provided.
引用
收藏
页数:19
相关论文
共 22 条
  • [1] Consideration of spent fuel pool island as an interim management option of spent nuclear fuel for Kori unit 3 & 4 during decommissioning of Kori site
    Songa, Maxwell
    Kim, Chang-Lak
    Kessel, David S.
    [J]. ENERGY STRATEGY REVIEWS, 2018, 21 : 163 - 171
  • [2] Examination of spent pressurized water reactor fuel rods after 15 years in dry storage
    Einziger, RE
    Tsai, HC
    Billone, MC
    Hilton, BA
    [J]. NUCLEAR TECHNOLOGY, 2003, 144 (02) : 186 - 200
  • [3] Conceptual design and analysis of a combined passive cooling system for both reactor and spent fuel of the pool-vessel reactor system
    Zhang, Wenwen
    Hao, Wentao
    Ye, Zishen
    Xie, Heng
    Shi, Lei
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2023, 414
  • [4] Investigation of the Thermal Performance of a Vertical Two-Phase Closed Thermosyphon as a Passive Cooling System for a Nuclear Reactor Spent Fuel Storage Pool
    Kusuma, Mukhsinun Hadi
    Putra, Nandy
    Antariksawan, Anhar Riza
    Susyadi
    Imawan, Ficky Augusta
    [J]. NUCLEAR ENGINEERING AND TECHNOLOGY, 2017, 49 (03) : 476 - 483
  • [5] Design of water purification system for Tehran research reactor spent nuclear fuels storage pool (wet storage)
    Aghoyeh, Reza Gholizadeh
    Khalafi, Hosein
    [J]. PROGRESS IN NUCLEAR ENERGY, 2011, 53 (01) : 119 - 124
  • [6] Suggestion on the safety classification of spent fuel dry storage in China's pressurized water reactor nuclear power plant
    Liu, Ting
    Qu, Yunhuan
    Meng, De
    Zhang, Qiaoer
    Lu, Xinhua
    [J]. 2017 3RD INTERNATIONAL CONFERENCE ON ENVIRONMENTAL SCIENCE AND MATERIAL APPLICATION (ESMA2017), VOLS 1-4, 2018, 108
  • [7] Design of make-up water system for Tehran research reactor spent nuclear fuels storage pool
    Aghoyeh, Reza Gholizadeh
    Khalafi, Hosein
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (10) : 2532 - 2537
  • [8] Regional overpower protection system analysis for the direct use of spent pressurized water reactor fuel in CANDU reactors (DUPIC)
    Jeong, CJ
    Choi, H
    [J]. IEEE TRANSACTIONS ON NUCLEAR SCIENCE, 2005, 52 (01) : 450 - 456
  • [9] Development of a Measurement System for Fission Gases Released from Spent Pressurized Water Reactor Fuel during Heat Treatment
    Lee, Jung-Won
    Park, Jang-Jin
    Park, Geun-Il
    [J]. ASIAN JOURNAL OF CHEMISTRY, 2012, 24 (07) : 3288 - 3290
  • [10] Determining initial enrichment, burnup, and cooling time of pressurized-water-reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden
    Favalli, A.
    Vo, D.
    Grogan, B.
    Jansson, P.
    Liljenfeldt, H.
    Mozin, V.
    Schwalbach, P.
    Sjoland, A.
    Tobin, S. J.
    Trellue, H.
    Vaccaro, S.
    [J]. NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 2016, 820 : 102 - 111