JP6650776B2 - フローダンパおよび蓄圧注水装置ならびに原子力設備 - Google Patents
フローダンパおよび蓄圧注水装置ならびに原子力設備 Download PDFInfo
- Publication number
- JP6650776B2 JP6650776B2 JP2016022399A JP2016022399A JP6650776B2 JP 6650776 B2 JP6650776 B2 JP 6650776B2 JP 2016022399 A JP2016022399 A JP 2016022399A JP 2016022399 A JP2016022399 A JP 2016022399A JP 6650776 B2 JP6650776 B2 JP 6650776B2
- Authority
- JP
- Japan
- Prior art keywords
- flow
- pipe
- jet
- vortex chamber
- outlet
- Prior art date
- Legal status (The legal status 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 status listed.)
- Active
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims description 105
- 238000002347 injection Methods 0.000 title claims description 43
- 239000007924 injection Substances 0.000 title claims description 43
- 239000002826 coolant Substances 0.000 claims description 57
- 230000002093 peripheral effect Effects 0.000 claims description 44
- 239000000498 cooling water Substances 0.000 claims description 29
- 239000012530 fluid Substances 0.000 claims description 8
- 238000001816 cooling Methods 0.000 description 22
- 239000000446 fuel Substances 0.000 description 7
- 230000004048 modification Effects 0.000 description 7
- 238000012986 modification Methods 0.000 description 7
- 238000010586 diagram Methods 0.000 description 6
- 230000004992 fission Effects 0.000 description 4
- 239000007789 gas Substances 0.000 description 4
- 238000009835 boiling Methods 0.000 description 3
- 230000007423 decrease Effects 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 230000001771 impaired effect Effects 0.000 description 3
- 239000007788 liquid Substances 0.000 description 3
- 230000001105 regulatory effect Effects 0.000 description 3
- 230000000712 assembly Effects 0.000 description 2
- 238000000429 assembly Methods 0.000 description 2
- 230000001276 controlling effect Effects 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 230000002035 prolonged effect Effects 0.000 description 2
- 238000011144 upstream manufacturing Methods 0.000 description 2
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 description 1
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 1
- 229910052796 boron Inorganic materials 0.000 description 1
- 229910001873 dinitrogen Inorganic materials 0.000 description 1
- 238000001704 evaporation Methods 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 230000002265 prevention Effects 0.000 description 1
- 239000013535 sea water Substances 0.000 description 1
Images
Classifications
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F15—FLUID-PRESSURE ACTUATORS; HYDRAULICS OR PNEUMATICS IN GENERAL
- F15D—FLUID DYNAMICS, i.e. METHODS OR MEANS FOR INFLUENCING THE FLOW OF GASES OR LIQUIDS
- F15D1/00—Influencing flow of fluids
- F15D1/0015—Whirl chambers, e.g. vortex valves
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/24—Promoting flow of the coolant
- G21C15/243—Promoting flow of the coolant for liquids
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
- G21C9/033—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency by an absorbent fluid
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
- G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
- G21C15/185—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps using energy stored in reactor system
-
- 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
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Fluid Mechanics (AREA)
- Mechanical Engineering (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Pipe Accessories (AREA)
Description
図1に示すように、原子力設備1は、原子炉5として加圧水型原子炉(PWR:Pressurized Water Reactor)が用いられている。この原子力設備1は、原子炉5において、一次冷却材を加熱した後、高温となった高温流体である一次冷却材(水)を冷却材ポンプ9により蒸気発生器7に送る。そして、原子力設備1は、蒸気発生器7において、高温となった一次冷却材を、二次冷却材と熱交換させることにより二次冷却材を蒸発させ、蒸発した二次冷却材(蒸気)をタービン22に送って発電機25を駆動させることにより、発電を行っている。なお、一次冷却材は、冷却材および中性子減速材として用いられる軽水である。
5 原子炉
6a コールドレグ(冷却材配管)
6b ホットレグ(冷却材配管)
6c クロスオーバーレグ(冷却材配管)
30 蓄圧注水装置
31 密封容器
32 冷却水
34 フローダンパ
35 渦室
36 大流量管(第二入口管)
37 小流量管(第一入口管)
38 出口管
39 出口
50、150、250、350、450 整流板
50A 側縁部
50B 外表面(接触面)
50C 内表面(接触面)
51、151、251 同心円
55 凹凸部(凹凸)
M 衝突点
P 直線
Claims (7)
- 円筒状の渦室と、
前記渦室の周縁部にその接線方向に沿って接続された第一入口管と、
前記第一入口管に対し所定の角度で前記周縁部に接続された第二入口管と、
前記渦室の中央部に形成された出口に接続された出口管と、
前記渦室の前記出口と前記周縁部との間の一部に配置され、前記第一入口管と前記第二入口管とから前記渦室に噴流が流入する場合、前記渦室に流入した前記第一入口管の噴流と前記第二入口管の噴流との衝突噴流を前記出口に向けて整流する整流板と、を備え、
前記整流板は、前記第一入口管の噴流と前記第二入口管の噴流との衝突点と前記出口の中心とを結ぶ直線を挟んだ両側に配置されていることを特徴とするフローダンパ。 - 前記整流板は、前記第一入口管から前記渦室に噴流が流入し、前記第二入口管から前記渦室に噴流が流入していない場合、前記渦室に流入した前記第一入口管の噴流を前記渦室の内周面に沿って整流することを特徴とする請求項1に記載のフローダンパ。
- 前記整流板は、前記出口と同心円の円弧状に形成されていることを特徴とする請求項1または2に記載のフローダンパ。
- 前記整流板は、前記噴流と接触する接触面に凹凸が設けられていることを特徴とする請求項1乃至3のいずれかに記載のフローダンパ。
- 前記第二入口管は、前記第一入口管よりも径が大きい管路であることを特徴とする請求項1乃至4のいずれかに記載のフローダンパ。
- 加圧状態で冷却水を貯留可能な密封容器と、前記出口管が前記密封容器の外部に引き出された形態で該密封容器内に配置される請求項1乃至5のいずれかに記載のフローダンパとを備える蓄圧注水装置。
- 原子炉で生成された熱により高温流体を発生させて冷却材配管で送り、当該高温流体を利用する原子力設備であって、
前記原子炉へ至る前記冷却材配管の途中に、請求項6に記載の蓄圧注水装置における前記密封容器の外部に引き出された前記出口管が接続され、かつ前記出口管の途中に弁が設けられたことを特徴とする原子力設備。
Priority Applications (4)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP2016022399A JP6650776B2 (ja) | 2016-02-09 | 2016-02-09 | フローダンパおよび蓄圧注水装置ならびに原子力設備 |
US15/748,413 US10900508B2 (en) | 2016-02-09 | 2017-01-27 | Flow damper, pressure-accumulation and water-injection apparatus, and nuclear installation |
EP17750099.8A EP3316263B1 (en) | 2016-02-09 | 2017-01-27 | Flow damper, pressure accumulation and water injection device, and nuclear power equipment |
PCT/JP2017/002926 WO2017138374A1 (ja) | 2016-02-09 | 2017-01-27 | フローダンパおよび蓄圧注水装置ならびに原子力設備 |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP2016022399A JP6650776B2 (ja) | 2016-02-09 | 2016-02-09 | フローダンパおよび蓄圧注水装置ならびに原子力設備 |
Publications (3)
Publication Number | Publication Date |
---|---|
JP2017141863A JP2017141863A (ja) | 2017-08-17 |
JP2017141863A5 JP2017141863A5 (ja) | 2019-02-07 |
JP6650776B2 true JP6650776B2 (ja) | 2020-02-19 |
Family
ID=59563292
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP2016022399A Active JP6650776B2 (ja) | 2016-02-09 | 2016-02-09 | フローダンパおよび蓄圧注水装置ならびに原子力設備 |
Country Status (4)
Country | Link |
---|---|
US (1) | US10900508B2 (ja) |
EP (1) | EP3316263B1 (ja) |
JP (1) | JP6650776B2 (ja) |
WO (1) | WO2017138374A1 (ja) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN112696550B (zh) * | 2020-12-28 | 2022-04-22 | 中国航空工业集团公司沈阳空气动力研究所 | 一种扩散整流的均流结构 |
Family Cites Families (29)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2258727A1 (de) | 1972-11-30 | 1974-06-06 | Siemens Ag | Verfahren fuer das zonenweise umsetzen von kernreaktorbrennelementen |
US4021298A (en) | 1974-01-29 | 1977-05-03 | Westinghouse Electric Corporation | Conversion of coal into hydrocarbons |
JPS60260898A (ja) | 1984-06-07 | 1985-12-24 | 株式会社日立製作所 | 原子炉制御棒駆動装置の洗浄装置 |
US4668465A (en) | 1984-10-26 | 1987-05-26 | Westinghouse Electric Corp. | Method and apparatus for remotely monitoring a process carried out in a containment structure |
FR2598247B1 (fr) | 1986-05-05 | 1988-09-09 | Novatome | Bouchon-couvercle du coeur d'un reacteur nucleaire a neutrons rapides |
JPS62184499U (ja) | 1986-05-15 | 1987-11-24 | ||
JPH0644060B2 (ja) | 1986-07-14 | 1994-06-08 | 三菱重工業株式会社 | 原子炉の緊急注水装置 |
FR2609833B1 (fr) | 1987-01-21 | 1991-10-18 | Novatome | Coeur d'un reacteur nucleaire et procede de chargement de ce coeur |
US4851183A (en) | 1988-05-17 | 1989-07-25 | The United States Of America As Represented By The United States Department Of Energy | Underground nuclear power station using self-regulating heat-pipe controlled reactors |
JP2909247B2 (ja) * | 1991-04-26 | 1999-06-23 | 三菱重工業株式会社 | 蓄圧器 |
JP2915682B2 (ja) * | 1992-03-16 | 1999-07-05 | 三菱重工業株式会社 | 原子炉緊急注水装置の蓄圧注水タンク |
JP3147586B2 (ja) | 1993-05-21 | 2001-03-19 | 株式会社日立製作所 | プラントの監視診断方法 |
US5817958A (en) | 1994-05-20 | 1998-10-06 | Hitachi, Ltd. | Plant monitoring and diagnosing method and system, as well as plant equipped with the system |
JPH10148692A (ja) | 1996-11-19 | 1998-06-02 | Mitsubishi Heavy Ind Ltd | 原子炉の冷却水緊急注入装置 |
KR100369247B1 (ko) | 2000-11-10 | 2003-01-24 | 한국전력공사 | 피동 작동 2단 유량전환 방법 및 장치 |
KR100594840B1 (ko) | 2003-05-21 | 2006-07-03 | 한국원자력연구소 | 풀 직접 냉각방식의 피동 안전등급 액체금속로잔열제거방법 및 잔열제거시스템 |
US7757715B2 (en) | 2006-11-28 | 2010-07-20 | Mitsubishi Heavy Industries, Ltd. | Accumulator and method of manufacturing flow damper |
US7881421B2 (en) | 2006-11-28 | 2011-02-01 | Mitsubishi Heavy Industries, Ltd. | Accumulator |
KR20080074568A (ko) | 2007-02-09 | 2008-08-13 | 한국원자력연구원 | 우수한 내식성을 갖는 고농도 철 함유 지르코늄 합금조성물 및 이의 제조방법 |
CN101315815B (zh) | 2008-04-28 | 2011-06-08 | 吕应中 | 快速增殖与转化核燃料的方法与装置 |
GB0819927D0 (en) | 2008-10-30 | 2008-12-10 | Nuclear Decommissioning Authority | Control fluid flow |
KR100966854B1 (ko) | 2009-01-14 | 2010-06-29 | 한국원자력연구원 | 부분잠김형 열교환기를 사용하는 소듐냉각 고속로의 완전 피동형 잔열제거계통 |
US8276669B2 (en) | 2010-06-02 | 2012-10-02 | Halliburton Energy Services, Inc. | Variable flow resistance system with circulation inducing structure therein to variably resist flow in a subterranean well |
US8893804B2 (en) * | 2009-08-18 | 2014-11-25 | Halliburton Energy Services, Inc. | Alternating flow resistance increases and decreases for propagating pressure pulses in a subterranean well |
JP5675134B2 (ja) | 2010-03-18 | 2015-02-25 | 三菱重工業株式会社 | 非常用システム |
KR20130098618A (ko) | 2012-02-28 | 2013-09-05 | 한국원자력연구원 | 사고조건 하의 원자로 내에서 우수한 내산화성을 나타내는 핵연료 피복관용 지르코늄 합금 조성물, 이를 이용하여 제조한 지르코늄 합금 핵연료 피복관 및 이의 제조방법 |
US10446280B2 (en) | 2012-04-18 | 2019-10-15 | Bwxt Mpower, Inc. | Control room for nuclear power plant |
KR101497893B1 (ko) | 2013-12-26 | 2015-03-05 | 한국과학기술원 | 가연성흡수체를 포함하는 제어봉 안내관 |
KR101551744B1 (ko) | 2014-08-11 | 2015-09-11 | 한국원자력연구원 | 원자로 및 그 동작 방법 |
-
2016
- 2016-02-09 JP JP2016022399A patent/JP6650776B2/ja active Active
-
2017
- 2017-01-27 EP EP17750099.8A patent/EP3316263B1/en active Active
- 2017-01-27 WO PCT/JP2017/002926 patent/WO2017138374A1/ja active Application Filing
- 2017-01-27 US US15/748,413 patent/US10900508B2/en active Active
Also Published As
Publication number | Publication date |
---|---|
EP3316263B1 (en) | 2019-10-16 |
EP3316263A1 (en) | 2018-05-02 |
JP2017141863A (ja) | 2017-08-17 |
WO2017138374A1 (ja) | 2017-08-17 |
US10900508B2 (en) | 2021-01-26 |
EP3316263A4 (en) | 2018-06-27 |
US20180218795A1 (en) | 2018-08-02 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CA2823960C (en) | Nuclear reactor control method and apparatus | |
US8908822B2 (en) | Nuclear reactor | |
US20180350472A1 (en) | Passive safe cooling system | |
EP3101658B1 (en) | Reactor system with a lead-cooled fast reactor | |
US10706974B2 (en) | Passive cooling system of containment building and nuclear power plant comprising same | |
KR101250479B1 (ko) | 안전보호용기를 구비한 피동형 비상노심냉각설비 및 이를 이용한 열 전달량 증가 방법 | |
CA2932602C (en) | Fast neutron reactor and neutron reflector block of a fast neutron reactor | |
KR101624561B1 (ko) | 격납부냉각계통 및 이를 구비한 원전 | |
JP6650776B2 (ja) | フローダンパおよび蓄圧注水装置ならびに原子力設備 | |
Raqué et al. | Design and 1D analysis of the safety systems for the SCWR fuel qualification test | |
EP3316264B1 (en) | Flow damper, pressure accumulation and water injection device, and nuclear power equipment | |
JP6614990B2 (ja) | フローダンパおよび蓄圧注水装置ならびに原子力設備 | |
KR100525708B1 (ko) | 비상노심냉각수 양방향 수평 분리판을 구비한가압경수로형 원자로 | |
JP6614989B2 (ja) | フローダンパおよび蓄圧注水装置ならびに原子力設備 | |
WO2003063177A1 (en) | Direct vessel injection system for emergency core cooling water using vertical injection pipe, sparger, internal spiral threaded injection pipe, and inclined injection pipe | |
Kang et al. | Thermal Sizing of Printed Circuit Steam Generator for Integral Reactor | |
KR100568762B1 (ko) | 비상노심냉각수가 최소 우회되는 직접주입노즐 | |
JP7480419B2 (ja) | 被動補助給水系統の被動凝縮タンク冷却システム | |
KR100900730B1 (ko) | 일체형원자로 유동혼합을 위한 증기발생기카세트 구조 | |
JPH07151475A (ja) | 復水器 |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
A521 | Written amendment |
Free format text: JAPANESE INTERMEDIATE CODE: A523 Effective date: 20181218 |
|
A621 | Written request for application examination |
Free format text: JAPANESE INTERMEDIATE CODE: A621 Effective date: 20181218 |
|
TRDD | Decision of grant or rejection written | ||
A01 | Written decision to grant a patent or to grant a registration (utility model) |
Free format text: JAPANESE INTERMEDIATE CODE: A01 Effective date: 20191224 |
|
A61 | First payment of annual fees (during grant procedure) |
Free format text: JAPANESE INTERMEDIATE CODE: A61 Effective date: 20200121 |
|
R150 | Certificate of patent or registration of utility model |
Ref document number: 6650776 Country of ref document: JP Free format text: JAPANESE INTERMEDIATE CODE: R150 |