PL3614396T3 - Sposób symulowania przepływu chłodziwa reaktora w rdzeniu i uproszczony model rdzenia dla sposobu - Google Patents

Sposób symulowania przepływu chłodziwa reaktora w rdzeniu i uproszczony model rdzenia dla sposobu

Info

Publication number
PL3614396T3
PL3614396T3 PL19191296T PL19191296T PL3614396T3 PL 3614396 T3 PL3614396 T3 PL 3614396T3 PL 19191296 T PL19191296 T PL 19191296T PL 19191296 T PL19191296 T PL 19191296T PL 3614396 T3 PL3614396 T3 PL 3614396T3
Authority
PL
Poland
Prior art keywords
core
reactor coolant
simplified model
simulating flow
simulating
Prior art date
Application number
PL19191296T
Other languages
English (en)
Inventor
Kyoung Ryun KIM
Min Soo Park
Ung Soo Kim
Jae Young Huh
Gyu Cheon Lee
Original Assignee
Kepco Engineering & Construction Company, Inc.
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Kepco Engineering & Construction Company, Inc. filed Critical Kepco Engineering & Construction Company, Inc.
Publication of PL3614396T3 publication Critical patent/PL3614396T3/pl

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/001—Mechanical simulators
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/02—Devices or arrangements for monitoring coolant or moderator
    • G21C17/032—Reactor-coolant flow measuring or monitoring
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
PL19191296T 2018-08-16 2019-08-12 Sposób symulowania przepływu chłodziwa reaktora w rdzeniu i uproszczony model rdzenia dla sposobu PL3614396T3 (pl)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
KR1020180095740A KR102167640B1 (ko) 2018-08-16 2018-08-16 노심부에서 원자로냉각재의 유동을 모사하는 방법 및 이에 사용되는 노심부단순화모델
EP19191296.3A EP3614396B1 (en) 2018-08-16 2019-08-12 Method of simulating flow of reactor coolant in a core and core simplified model for the method

Publications (1)

Publication Number Publication Date
PL3614396T3 true PL3614396T3 (pl) 2021-10-11

Family

ID=67614505

Family Applications (1)

Application Number Title Priority Date Filing Date
PL19191296T PL3614396T3 (pl) 2018-08-16 2019-08-12 Sposób symulowania przepływu chłodziwa reaktora w rdzeniu i uproszczony model rdzenia dla sposobu

Country Status (3)

Country Link
EP (1) EP3614396B1 (pl)
KR (1) KR102167640B1 (pl)
PL (1) PL3614396T3 (pl)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114282460B (zh) * 2021-12-31 2023-05-16 西安交通大学 一种铅铋快堆堆芯热工水力特性分析方法
CN119694617B (zh) * 2024-12-23 2025-11-25 中国原子能科学研究院 反应堆燃料组件的装载的方法以及铅铋堆的装载的方法
CN120452857A (zh) * 2025-04-30 2025-08-08 中国原子能科学研究院 堆芯模拟装置及其制备方法

Family Cites Families (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2316832A (en) * 1934-12-04 1943-04-20 Aghnides Elie Fluid mixing device
GB2329134B (en) * 1997-08-15 2001-02-14 Reckitt & Colman Inc Improvements to apparatus
KR101104894B1 (ko) * 2009-10-27 2012-01-12 한국수력원자력 주식회사 열수력 안전해석코드를 이용한 원자로 노심 평가방법
KR100957066B1 (ko) * 2009-11-27 2010-05-13 (주)에네시스 다공성 매질 특성을 이용한 원자로 노심 해석 방법
KR101512644B1 (ko) 2013-10-31 2015-04-17 한국원자력연구원 초고온 가스로 노심 입구의 가스 냉각재 균일유동 구조
TWI873632B (zh) 2015-02-27 2025-02-21 日商中外製藥股份有限公司 Il-6受體抗體用於製備醫藥組成物的用途
KR101754287B1 (ko) * 2016-08-08 2017-07-06 한국원자력연구원 가변형 노심 시뮬레이터
CN106340329B (zh) * 2016-10-31 2017-12-15 中国核动力研究设计院 反应堆热工水力模拟试验装置及流体动力学特性模拟方法
CN106504803B (zh) * 2016-11-18 2017-12-15 中国核动力研究设计院 一种用于反应堆一回路冷却剂活化源项验证的实验装置
CN106531240B (zh) * 2016-11-25 2018-03-20 中国核动力研究设计院 一种换热器、反应堆模拟系统及其自然循环停滞再启动模拟实验方法
CN106803431B (zh) * 2017-01-22 2017-12-12 中国核动力研究设计院 可精确测量堆芯流量的外置式下降腔布置装置及测量方法
CN106683722B (zh) * 2017-02-22 2017-12-19 哈尔滨工程大学 棒束通道流动测压实验装置
CN107527664A (zh) * 2017-07-31 2017-12-29 中国核动力研究设计院 一种模拟核反应堆流体自然循环流动特性的方法
CN107452430A (zh) * 2017-09-01 2017-12-08 哈尔滨工程大学 一种可伸缩的棒束通道多物理场可视化本体设计

Also Published As

Publication number Publication date
KR20200020266A (ko) 2020-02-26
KR102167640B1 (ko) 2020-10-19
EP3614396B1 (en) 2021-03-24
EP3614396A1 (en) 2020-02-26

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