WO2014090107A1 - 一种事故工况下延长蒸汽发生器满溢时间的方法 - Google Patents
一种事故工况下延长蒸汽发生器满溢时间的方法 Download PDFInfo
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- WO2014090107A1 WO2014090107A1 PCT/CN2013/088608 CN2013088608W WO2014090107A1 WO 2014090107 A1 WO2014090107 A1 WO 2014090107A1 CN 2013088608 W CN2013088608 W CN 2013088608W WO 2014090107 A1 WO2014090107 A1 WO 2014090107A1
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- steam generator
- auxiliary feed
- water
- auxiliary
- pumps
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- 238000000034 method Methods 0.000 title claims abstract description 18
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 63
- 230000010485 coping Effects 0.000 description 1
- 238000002347 injection Methods 0.000 description 1
- 239000007924 injection Substances 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
- G21D3/06—Safety arrangements responsive to faults within the plant
-
- 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
Definitions
- the invention belongs to a method for coping with an accident of a pressurized water reactor nuclear power plant, and particularly relates to a method for prolonging the overflow time of a steam generator under an accident condition of a pressurized water reactor nuclear power plant.
- the pressurized water reactor nuclear power plant will cause all auxiliary feed pumps to start. If the auxiliary feed water flow is greater than the steam flow, the secondary side water load of the steam generator will continue to increase. If the operator fails to reduce the auxiliary feed water flow in time, the steam generator will overflow.
- the auxiliary water supply flow can be reasonably controlled without affecting the residual heat of the SG, and the SG can reach the overflow time, thereby prolonging the time for the operator not to interfere with the accident and reducing the operator's time. Mistakes. In the end, after the operator intervention, the SG will not overflow.
- the object of the present invention is to provide a method for prolonging the overflow time of a steam generator under an accident condition of a pressurized water reactor nuclear power plant, which can be set in the accident of starting the auxiliary feed water pump of the pressurized water reactor nuclear power plant.
- the steam generator water level reaches a high fixed value and the corresponding auxiliary feed water pump "signal is used to adjust the auxiliary feed water flow of the steam generator, ensuring that the steam generator has sufficient heat capacity to ensure the pile.
- the SG is extended to overflow time, thereby prolonging the time for the operator not to interfere with the accident and reducing the operator's mistakes.
- the present invention is achieved by a method for prolonging a steam generator overflow time under an accident condition of a pressurized water reactor nuclear power plant, which includes the following steps:
- the second enthalpy is that as the water level of the secondary side of the SG increases, when the secondary water level of any SG is higher than the design setting value, the auxiliary feed water pump will be stopped according to the following conditions:
- the third parameter is that if the SG water level is low and the same SG water supply flow rate is low due to the stoppage of the auxiliary feed pump, the all-stop auxiliary feed water pump will be automatically restarted to ensure that the SG secondary side remains sufficient. The amount of water loaded.
- the invention has the advantages that the method automatically adjusts the flow rate of the steam generator auxiliary feed water by increasing the protection control signal, and prolongs the overflow time of the steam generator under the premise of ensuring the safety of the core, thereby prolonging the operator's non-intervention accident. Time to reduce the operator's mistakes.
- Figure 1 is a flow chart of a method for extending the steam generator overflow time under an accident condition of a pressurized water reactor nuclear power plant.
- the auxiliary feed water flow is adjusted by setting the "steam generator water level to reach the high fixed value and the corresponding auxiliary feed pump" signal, and the SG reaches the overflow time, thereby prolonging the operator. Do not interfere with the accident time, reduce the operator's mistakes. After the intervention of the operator, the SG is not full.
- the relevant equipment involved in the scenario of prolonging the steam generator overflow time under accident conditions includes control logic and operator interface.
- the operator interface is an indication and reset interface that provides the operator with the signals "Stop 2 auxiliary feed pumps” and "Stop 1 auxiliary feed pump”.
- a method for prolonging the overflow time of a steam generator under an accident condition of a pressurized water reactor nuclear power plant is as follows:
- auxiliary feed pump When an accident occurs in a nuclear power plant that requires the start of all auxiliary feed pumps, the injection of a larger flow of auxiliary feed water will result in a gradual increase in the water level on the secondary side of the SG. As the water level on the secondary side of the SG increases, when the water level on the secondary side of any SG is higher than the design setting value, the auxiliary feed pump will be stopped according to the following conditions:
- the accident intervention and treatment are carried out according to the corresponding accident handling procedures.
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Control Of Steam Boilers And Waste-Gas Boilers (AREA)
- Structures Of Non-Positive Displacement Pumps (AREA)
- Control Of Positive-Displacement Pumps (AREA)
- Control Of Turbines (AREA)
Abstract
一种用于压水堆核电厂事故工况下延长蒸汽发生器满溢时间的方法,属于压水堆核电厂事故应对方法的领域,包括如下步骤,第一步:发生了导致所有辅助给水泵启动的事故;第二步:停运辅助给水泵;第三步:判断是否需要再启动辅助给水泵。该方法通过增加保护控制信号,自动调节蒸汽发生器辅助给水的流量,在保证堆芯安全的前提下延长了蒸汽发生器发生满溢的时间,从而延长操纵员不干预事故的时间,减小操纵员的失误。
Description
一种事故工况下延长蒸汽发生器满溢时间的方法
技术领域
本发明属于一种压水堆核电厂事故应对方法, 具体涉及一种用于压水堆 核电厂事故工况下延长蒸汽发生器满溢时间的方法。
背景技术
压水堆核电厂在部分事故中将导致所有辅助给水泵全部启动, 如果辅助 给水流量大于蒸汽流量, 将造成蒸汽发生器二次侧水装量持续增加。 如果操 纵员未能及时减小辅助给水流量, 将造成蒸汽发生器满溢。
国内现役核电站没有设置在这类事故工况下防止 SG满溢的措施, 为了 防止事故工况下 SG满溢就要求操纵员尽快采取干预措施, 对操纵员的要求 就比较高, 容易发生误操作。
通过设置合理的自动保护措施, 在不影响 SG带走堆芯余热的情况下, 合理控制辅助给水流量, 延长 SG达到满溢的时间, 从而延长操纵员不干预 事故的时间, 减小操纵员的失误。 在操纵员干预后最终实现 SG不会发生满 溢。
发明内容
本发明的目的是提供一种用于压水堆核电厂事故工况下延长蒸汽发生器 满溢时间的方法, 它能够在压水堆核电厂的一些启动辅助给水泵的事故中, 通过设置 "蒸汽发生器水位达到高定值停运相应的辅助给水泵"信号来调节 蒸汽发生器的辅助给水流量, 在确保蒸汽发生器有足够的带热能力来保证堆
芯安全的前提下, 延长 SG达到满溢的时间, 从而延长操纵员不干预事故的 时间, 减小操纵员的失误。 本发明是这样实现的, 一种用于压水堆核电厂事故工况下延长蒸汽发生 器满溢时间的方法, 它包括如下歩骤,
第一歩: 发生了导致所有辅助给水泵启动的事故;
第二歩: 停运辅助给水泵;
第三歩: 判断是否需要再启动辅助给水泵。
所述的第二歩为随着 SG二次侧水位的增加, 当任一 SG二次侧水位高 于设计整定值时, 将根据如下情况停运辅助给水泵:
在 4台辅助给水泵均启动运行的情况下, 如果有一台蒸汽发生器的水位 达到高高水位整定值, 则停运其中 2台辅助给水泵;
如果只有 3台辅助给水泵启动在运行, 则只用停运 1台辅助给水泵。 所述的第三歩为如果因停运辅助给水泵导致 SG水位低低与同一台 SG 给水流量低符合信号产生, 则将自动重新启动所有停运的辅助给水泵, 确保 SG二次侧保持足够的水装量。
本发明的优点是, 该方法通过增加保护控制信号, 自动调节蒸汽发生器 辅助给水的流量, 在保证堆芯安全的前提下延长了蒸汽发生器发生满溢的时 间, 从而延长操纵员不干预事故的时间, 减小操纵员的失误。
附图说明 图 1为一种用于压水堆核电厂事故工况下延长蒸汽发生器满溢时间的方 法的流程图。
具体实施方式
下面结合附图和实施例对本发明进行详细介绍:
(一) 基本原理
在核电厂发生启动辅助给水泵的事故下, 通过设置 "蒸汽发生器水位达 到高定值停运相应的辅助给水泵"信号来调节辅助给水流量, 延长 SG达到 满溢的时间, 从而延长操纵员不干预事故的时间, 减小操纵员的失误。 在操 纵员干预后最终实现 SG不满溢。
(二) 主要设备
事故工况下延长蒸汽发生器满溢时间的方案中涉及的相关设备包括控制 逻辑及操纵员接口。
为防止核电厂在发生启动辅助给水泵的事故下蒸汽发生器满溢, 核电厂 增设如下控制逻辑:
在 4台辅助给水泵均启动的情况下, 如果有一台蒸汽发生器的水位达到 设定的高水位整定值,则停运 2台辅助给水泵;若只有 3台辅助给水泵启动, 如果有一台蒸汽发生器的水位达到设定的高水位整定值, 则只停运 1台辅助 给水泵。 即在事故情况下维持有两台辅助给水泵运行。
操纵员接口是提供操纵员 "停运 2台辅助给水泵" 、 "停运 1台辅助给 水泵"信号的指示和复位接口。
一种用于压水堆核电厂事故工况下延长蒸汽发生器满溢时间的方法, 具 体运行流程如下:
第一歩: 发生了导致所有辅助给水泵启动的事故;
在核电厂发生需要启动所有辅助给水泵的事故时, 较大流量的辅助给水 注入将导致 SG二次侧水位逐渐增加。
随着 SG二次侧水位的增加, 当任一 SG二次侧水位高于设计整定值时, 将根据如下情况停运辅助给水泵:
在 4台辅助给水泵均启动运行的情况下, 如果有一台蒸汽发生器的水位 达到高高水位整定值, 则停运其中 2台辅助给水泵;
如果只有 3台辅助给水泵启动在运行, 则只用停运 1台辅助给水泵。
§Ρ: 在事故情况下只需要有两台辅助给水泵运行, 这样既可以保证堆芯 安全, 又将延长蒸汽发生器发生满溢的时间。
第三歩: 判断是否需要再启动辅助给水泵;
如果因停运辅助给水泵导致 SG水位低低与同一台 SG给水流量低符合 信号产生, 则将自动重新启动所有停运的辅助给水泵, 确保 SG二次侧保持 足够的水装量。
操纵员干预之后根据相应的事故处理规程进行事故干预和处理。
Claims
1、 一种用于压水堆核电厂事故工况下延长蒸汽发生器满溢时间的方法, 其特征在于: 它包括如下歩骤,
第一歩: 发生了导致所有辅助给水泵启动的事故;
第二歩: 停运辅助给水泵;
第三歩: 判断是否需要再启动辅助给水泵。
2、 如权利要求 1 所述的一种用于压水堆核电厂事故工况下延长蒸汽发 生器满溢时间的方法, 其特征在于: 所述的第二歩为随着 SG二次侧水位的 增加, 当任一 SG二次侧水位高于设计整定值时, 将根据如下情况停运辅助 给水泵:
在 4台辅助给水泵均启动运行的情况下, 如果有一台蒸汽发生器的水位 达到高高水位整定值, 则停运其中 2台辅助给水泵;
如果只有 3台辅助给水泵启动在运行, 则只用停运 1台辅助给水泵。
3、 如权利要求 1 所述的一种用于压水堆核电厂事故工况下延长蒸汽发 生器满溢时间的方法, 其特征在于: 所述的第三歩为如果因停运辅助给水泵 导致 SG水位低低与同一台 SG给水流量低符合信号产生, 则将自动重新启 动所有停运的辅助给水泵, 确保 SG二次侧保持足够的水装量。
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CN113421676A (zh) * | 2021-06-18 | 2021-09-21 | 中国核动力研究设计院 | 一种核电厂事故规程整定值的确定方法及装置 |
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CN111651713B (zh) * | 2020-06-10 | 2023-10-20 | 三门核电有限公司 | 一种核电厂运行期间蒸汽发生器腐蚀产物沉积计算方法 |
CN113436768B (zh) * | 2021-06-23 | 2022-05-20 | 中国核动力研究设计院 | 一种用于核电厂稳压器水位整定值的确定方法 |
CN114251646B (zh) * | 2021-11-15 | 2023-12-26 | 中广核研究院有限公司 | 适用于主泵启停工况的蒸汽发生器液位控制方法 |
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