KR920003331A - 부하가 증가하는 경우의 원자로 보호 방법 - Google Patents
부하가 증가하는 경우의 원자로 보호 방법 Download PDFInfo
- Publication number
- KR920003331A KR920003331A KR1019910012138A KR910012138A KR920003331A KR 920003331 A KR920003331 A KR 920003331A KR 1019910012138 A KR1019910012138 A KR 1019910012138A KR 910012138 A KR910012138 A KR 910012138A KR 920003331 A KR920003331 A KR 920003331A
- Authority
- KR
- South Korea
- Prior art keywords
- reactor
- emergency stop
- operating temperature
- temperature
- core
- Prior art date
Links
- 238000000034 method Methods 0.000 claims 8
- 239000012530 fluid Substances 0.000 claims 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims 2
- 230000004308 accommodation Effects 0.000 claims 1
- 239000000446 fuel Substances 0.000 claims 1
- 230000000149 penetrating effect Effects 0.000 claims 1
- 238000010586 diagram Methods 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
-
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/08—Regulation of any parameters in the plant
- G21D3/10—Regulation of any parameters in the plant by a combination of a variable derived from neutron flux with other controlling variables, e.g. derived from temperature, cooling flow, pressure
-
- 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
-
- 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)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
Claims (6)
- 원자력(DT)이 비상정지 한계(LP)에 도달하는 경우에 원자로의 비상 정지가 시동되도록, 원자로의 부하가 증가하는 경우 원자로 특히, 가압수형 원자로를 보호하는 방법에 있어서, 상기 비상 정지 한계는 원자로의 낮은 작동 온도(ST)에서 낮아지는 것을 특징으로 하는 원자로 보호방법.
- 제1항에 있어서, 상기 원자로는, 원자핵 반응이 일어나는 연료봉들을 내장하고, 노심의 상부와 하부사이에 분포되어 열로 전환되는 원자력을 발생시키는 노심(2)와, 열 교환 유체가 노심을 통해 흐르게하고 배출덕트(6)을 경유하여 노심을 떠나게 하기 위해 인입 덕트(4)를 경유하여 노심속으로 관통하게 함으로써 상기 열을 제거하여 그 열을 변하는 수요을 갖는 열 수납기(10)으로 전달하는 열 교환 회로(4, 6, 8)과, 상기 원자핵 반응을 제어하기 위해 상부로부터 상기 코어속으로 제어된 방식으로 관통하는 제어용 클러스터(12)와, 상기 원자력을 나타내는 총 출력 신호(DT)를 전달하는 적어도 하나의 출력 측정 시스템(14)와, 상기 열 교환 유체의 온도인 작동 온도를 나타내는 작동 온도 신호(ST)를 제공하는 온도 측정 시스템(18)과, 적어도 대략 수요에 상당하는 화력을 상기 열 수납기가 받도록 특히 상기 열수납기(10)의 수용의 변화의 함수로서 상기 제어봉 클러스터(12)의 일부에 작용하는 출력 제어 시스템(24)와, 상기 원자핵 반응을 신속하게 정지시키기 위해 상기 제어봉 집단을 상기 노심속으로 관통시키는 비상 정지 신호를 전달할 수 있고 그러기 위해서 적어도 상기 총 출력 신호 및 상기 작동온도 신호를 받아서 상기 총 출력 신호(ET)로 나타낸 원자력이 적어도 상기 온도 신호(ST)에 기초하여 한정된 비상 정지 한계(LP)를 초과할 때 상기 비상 정지 신호(AR)을 전달하는 과출력 보호 시스템(30)을 구비하고, 상기 비상 정지 한계(LP)는 기준 온도(TR) 이하인 작동 온도(T)에 상당하는 상기 온도 신호(ST)값에서 낮아지는 것을 특징으로 하는 원자로 보호방법.
- 제2항에 있어서, 상기 비상 정지 한계(LP)는 상기 작동 온도(ST)의 함수로서 양의 기울기 법칙을 따르는 것을 특징으로 하는 원자로 보호 방법.
- 제3항에 있어서, 상기 비상 정지 한계(LP)에 적용 가능한 상기 양의 기울기 법칙은 직선형 법칙인 것을 특징으로 하는 원자로 보호 방법.
- 제2항에 있어서, 상기 기준 온도(TR)은 270℃ 내지 320℃의 범위에 있고, 상기 방법이 가압수형 원자로에 적용될 때 바람직하게는 290℃ 내지 300℃의 범위에 있는 것을 특징으로 하는 원자로 보호방법.
- 제5항에 있어서, 상기 작동 온도(ST)는 상기 기준 온도(TR)보다 20℃ 낮고, 상기 비상 정지 한계(LP)는 상기 작동 온도가 상기 기준 온도보다 더 클때 갖는 값의 1/2보다 낮은 값을 갖는 것을 특징으로 하는 원자로 보호방법.※ 참고사항 : 최초출원 내용에 의하여 공개되는 것임.
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR9009094A FR2665013B1 (fr) | 1990-07-17 | 1990-07-17 | Procede de protection d'un reacteur nucleaire en cas d'elevation de sa charge. |
FR9009094 | 1990-07-17 |
Publications (2)
Publication Number | Publication Date |
---|---|
KR920003331A true KR920003331A (ko) | 1992-02-29 |
KR100237114B1 KR100237114B1 (ko) | 2000-01-15 |
Family
ID=9398802
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
KR1019910012138A KR100237114B1 (ko) | 1990-07-17 | 1991-07-16 | 부하가 증가하는 경우의 원자로 보호 방법 |
Country Status (9)
Country | Link |
---|---|
US (1) | US5169592A (ko) |
EP (1) | EP0467787B1 (ko) |
JP (1) | JPH0511092A (ko) |
KR (1) | KR100237114B1 (ko) |
CN (1) | CN1058286A (ko) |
DE (1) | DE69105386T2 (ko) |
ES (1) | ES2064949T3 (ko) |
FR (1) | FR2665013B1 (ko) |
ZA (1) | ZA915585B (ko) |
Families Citing this family (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5309485A (en) * | 1992-07-06 | 1994-05-03 | General Electric Company | Core automated monitoring system |
US5528639A (en) * | 1994-08-01 | 1996-06-18 | General Electric Company | Enhanced transient overpower protection system |
CN106887265B (zh) * | 2017-03-14 | 2018-05-15 | 国核电力规划设计研究院有限公司 | 一种球床模块式高温气冷堆的启停堆系统 |
Family Cites Families (10)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3979255A (en) * | 1973-09-04 | 1976-09-07 | Combustion Engineering, Inc. | Method for operating a system with a variable excursion margin setpoint |
JPS5552998A (en) * | 1978-10-16 | 1980-04-17 | Hitachi Ltd | Reactor recirculation flow rate control device |
US4308099A (en) * | 1979-01-22 | 1981-12-29 | The Babcock & Wilcox Company | Nuclear reactor safety system |
FR2542493B1 (fr) * | 1983-03-11 | 1985-12-27 | Framatome Sa | Dispositif de determination rapide et precise de la puissance d'un reacteur nucleaire a eau sous pression |
JPS59184895A (ja) * | 1983-04-06 | 1984-10-20 | 株式会社日立製作所 | 原子炉の負荷追従制御方法 |
US4637911A (en) * | 1984-07-24 | 1987-01-20 | Massachusetts Institute Of Technology | Apparatus and method for closed-loop control of reactor power |
JPS629413A (ja) * | 1985-07-05 | 1987-01-17 | Hitachi Ltd | 発電プラントの制御装置 |
US4738818A (en) * | 1986-09-29 | 1988-04-19 | Westinghouse Electric Corp. | Feedwater control in a PWR following reactor trip |
FR2610446B1 (fr) * | 1987-01-30 | 1991-11-29 | Framatome Sa | Procede de determination du seuil d'alarme du rapport d'echauffement critique, dispositif de mise en oeuvre, et procede de pilotage d'un reacteur nucleaire |
US4975238A (en) * | 1988-09-01 | 1990-12-04 | Mpr, Inc. | Control system for a nuclear steam power plant |
-
1990
- 1990-07-17 FR FR9009094A patent/FR2665013B1/fr not_active Expired - Lifetime
-
1991
- 1991-07-16 JP JP3201409A patent/JPH0511092A/ja active Pending
- 1991-07-16 KR KR1019910012138A patent/KR100237114B1/ko not_active IP Right Cessation
- 1991-07-17 ZA ZA915585A patent/ZA915585B/xx unknown
- 1991-07-17 DE DE69105386T patent/DE69105386T2/de not_active Expired - Lifetime
- 1991-07-17 CN CN91104799A patent/CN1058286A/zh active Pending
- 1991-07-17 ES ES91402001T patent/ES2064949T3/es not_active Expired - Lifetime
- 1991-07-17 EP EP91402001A patent/EP0467787B1/fr not_active Expired - Lifetime
- 1991-07-17 US US07/731,330 patent/US5169592A/en not_active Expired - Lifetime
Also Published As
Publication number | Publication date |
---|---|
FR2665013B1 (fr) | 1992-09-18 |
EP0467787A1 (fr) | 1992-01-22 |
CN1058286A (zh) | 1992-01-29 |
KR100237114B1 (ko) | 2000-01-15 |
DE69105386D1 (de) | 1995-01-12 |
ES2064949T3 (es) | 1995-02-01 |
EP0467787B1 (fr) | 1994-11-30 |
US5169592A (en) | 1992-12-08 |
JPH0511092A (ja) | 1993-01-19 |
FR2665013A1 (fr) | 1992-01-24 |
ZA915585B (en) | 1992-04-29 |
DE69105386T2 (de) | 1995-04-20 |
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