WO2023226394A1 - 一种高温气冷堆堆芯等温温度系数测量方法 - Google Patents
一种高温气冷堆堆芯等温温度系数测量方法 Download PDFInfo
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- 238000000034 method Methods 0.000 title claims abstract description 21
- 238000010438 heat treatment Methods 0.000 claims description 18
- 230000009257 reactivity Effects 0.000 claims description 17
- 239000001307 helium Substances 0.000 claims description 11
- 229910052734 helium Inorganic materials 0.000 claims description 11
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 claims description 11
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 7
- 239000002918 waste heat Substances 0.000 claims description 3
- 238000002360 preparation method Methods 0.000 claims description 2
- 230000000630 rising effect Effects 0.000 abstract description 6
- 239000002826 coolant Substances 0.000 description 3
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 2
- 229910052796 boron Inorganic materials 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 238000005259 measurement Methods 0.000 description 2
- 238000000691 measurement method Methods 0.000 description 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 238000012937 correction Methods 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 229910002804 graphite Inorganic materials 0.000 description 1
- 239000010439 graphite Substances 0.000 description 1
- 238000013031 physical testing Methods 0.000 description 1
- 239000002574 poison Substances 0.000 description 1
- 231100000614 poison Toxicity 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 238000012546 transfer Methods 0.000 description 1
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/104—Measuring reactivity
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/112—Measuring temperature
Definitions
- the present disclosure belongs to the field of nuclear reactor core physical testing, and relates to a method for measuring the isothermal temperature coefficient of a high-temperature gas-cooled reactor core.
- the high-temperature gas-cooled reactor nuclear power unit is an advanced reactor type with the characteristics of fourth-generation nuclear power technology. It is one of the main reactor types in the development of nuclear power today. Its most important characteristics are that it has a very large heat capacity and good core negative temperature reactivity. Coefficient is a characteristic of the inherent safety of high-temperature gas-cooled reactors.
- the temperature of the primary circuit of the pressurized water reactor nuclear power unit is adjusted at T ref ⁇ 1°C, and the linear segment is selected for processing to obtain the isothermal temperature coefficient.
- the published patent CN201611052690.0 uses a correction method to compensate for the control rod position and critical boron concentration, and can obtain relatively satisfactory results.
- High-temperature gas-cooled reactors use graphite as the moderator and helium as the coolant.
- the coolant does not contain boron, a soluble poison, and the heat capacity of the high-temperature gas-cooled reactor is larger.
- the coolant helium and heat transfer rate are higher than those of pressurized water reactors or pressurized water reactors.
- Liquid metal-cooled fast reactors are much slower, so the isothermal temperature coefficient measurement method used in pressurized water reactors or liquid metal-cooled fast reactors is not suitable for high-temperature gas-cooled reactors, and will produce large measurement errors.
- the purpose of this disclosure is to overcome the above-mentioned shortcomings of the prior art and provide a method for measuring the isothermal temperature coefficient of a high-temperature gas-cooled reactor core, which can accurately measure the isothermal temperature coefficient of a high-temperature gas-cooled reactor core.
- the method for measuring the isothermal temperature coefficient of the high-temperature gas-cooled reactor core disclosed in the present disclosure includes the following steps:
- the main helium blower operates at reduced frequency to gradually cool down the primary circuit
- ⁇ T 1 ⁇ 2°C.
- step 11 The specific process of step 11) is:
- step 17 put in a water-cooled wall or take the waste heat out of the system to gradually cool down the primary loop.
- the default value is 2pcm/°C.
- the high-temperature gas-cooled reactor isothermal temperature coefficient ⁇ (T) rises and the high-temperature gas-cooled reactor isothermal temperature coefficient ⁇ (T) decreases to calculate the high-temperature gas at B°C.
- the isothermal temperature coefficient of the cold reactor core avoids the measurement error caused by the large thermal capacity buffer of the high-temperature gas-cooled reactor, thereby obtaining a more accurate isothermal temperature coefficient.
- the disclosed method for measuring the isothermal temperature coefficient of the high-temperature gas-cooled reactor core includes the following steps:
- the main helium blower is operated at a reduced frequency, and a water-cooled wall is put in or the waste heat is exported into the system to gradually cool down the primary circuit;
- ⁇ T 1 ⁇ 2°C
- This disclosure aims at the problems of large heat capacity and large thermal inertia of the high-temperature gas-cooled reactor core. It heats up the primary circuit in a large range, and measures the reactivity corresponding to each temperature step to obtain the temperature-reactivity within a certain temperature range. Fit the curve, and according to the slope of the fitting curve at the determined temperature, obtain the isothermal temperature coefficient corresponding to the rising edge of this temperature. The same cooling operation is performed to obtain the isothermal temperature coefficient of the falling edge of this temperature. The above operations are performed cyclically until the difference between the two isothermal temperature coefficients is ⁇ 2pcm/°C; the final isothermal temperature coefficient is the average of the rising and falling edge isothermal temperature coefficients.
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- 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)
Abstract
本公开提出一种高温气冷堆堆芯等温温度系数测量方法,包括以下步骤:1)绘制一回路温度上升段范围内的温度-反应性拟合曲线,将B℃处温度-反应性拟合曲线的斜率作为高温气冷堆等温温度系数α(T) 上升;2)绘制一回路温度下降段范围内的温度-反应性拟合曲线,将B℃处温度-反应性拟合曲线的斜率作为高温气冷堆等温温度系数α(T) 下降;3)计算B℃处高温气冷堆堆芯的等温温度系数α(T)=[α(T) 上 升+α(T) 下降]/2,该方法能够准确测量高温气冷堆堆芯的等温温度系数。
Description
本公开属于核反应堆堆芯物理试验领域,涉及一种高温气冷堆堆芯等温温度系数测量方法。
高温气冷堆核电机组是具有第四代核电技术特征的先进堆型,是当今核电发展的主力堆型之一,其最主要的特点是具有非常大的热容量和良好的堆芯负温度反应性系数,是高温气冷堆固有安全性的特点。
已公开的专利CN201811602298.8中,压水堆核电机组一回路温度在T
ref±1℃进行调整,选取线性段进行处理得到等温温度系数。已公开的专利CN201611052690.0采用修正方法对控制棒棒位和临界硼浓度进行补偿修正,可以得到较为满意的结果。
高温气冷堆由于采用石墨作为慢化剂、氦气作为冷却剂,冷却剂中不含可溶毒物硼,且高温气冷堆热容量较大,冷却剂氦气和传热速率比压水堆或者液态金属冷却快堆都慢的多,因此压水堆或者液态金属冷却快堆所采用的等温温度系数测量方法不适用于高温气冷堆,会产生很大的测量误差。
发明内容
本公开的目的在于克服上述现有技术的缺点,提供了一种高温气冷堆堆芯等温温度系数测量方法,该方法能够准确测量高温气冷堆堆芯的等温温度系数。
为达到上述目的,本公开的高温气冷堆堆芯等温温度系数测量方法包括以下步骤:
1)绘制一回路温度上升段范围内的温度-反应性拟合曲线,将B℃处温度-反应性拟合曲线的斜率作为高温气冷堆等温温度系数α(T)
上升;
2)绘制一回路温度下降段范围内的温度-反应性拟合曲线,将B℃处温度-反应性拟合曲线的斜率作为高温气冷堆等温温度系数α(T)
下降;
3)计算B℃处高温气冷堆堆芯的等温温度系数α(T)=[α(T)
上升+α(T)
下
降]/2。
具体包括以下步骤:
11)进行前期准备工作;
12)将一回路加热温度至A℃,停止一回路加热,在该温度下主氦风机的全速稳定运行超过Nmin后,记录该温度下的反应性;
13)重新投入一回路加热,待一回路温度升高ΔT℃后,停止一回路加热,再保持一回路的温度稳定;
14)等待超过Nmin后,记录当前温度下的反应性;
15)重复步骤13)至步骤14),直至一回路温度达到C℃为止;
16)绘制一回路温度上升段范围内的温度-反应性拟合曲线,将B℃处温度-反应性拟合曲线的斜率作为高温气冷堆等温温度系数α(T)
上升,其中,A<B<C;
17)主氦风机降频运行,对一回路进行逐步降温;
18)待一回路温度降低ΔT℃后,切除水冷壁,保持一回路温度稳定;
19)在该温度下保持稳定超过Nmin后,记录当前温度下的反应性;
110)重复步骤17)至步骤19),直至一回路温度降低至A℃为止;
111)绘制一回路温度下降段范围内的温度-反应性拟合曲线,将B℃处温度-反应性拟合曲线的斜率作为高温气冷堆等温温度系数α(T)
下降;
112)计算差值Δα=α(T)
上升-α(T)
下降;
113)重复步骤11)至步骤112),直至∣Δα∣≤预设值为止;
116)计算B℃处高温气冷堆堆芯的等温温度系数α(T)=[α(T)
上升+α(T)
下降]/2。
B=250;C=260;A=240。
ΔT的取值范围在1~2℃。
步骤11)的具体过程为:
11a)将吸收球全部至于反应堆顶部;
11b)将控制棒至于临界棒位处;
11c)反应堆功率维持在核加热点以下;
11d)反应性仪已经投入监测反应性;
11e)主氦风机全速稳定运行,一回路加热投入。
步骤17)中,投入水冷壁或者将余热导出系统对一回路进行逐步降温。
N=30。
预设值为2pcm/℃。
本公开具有以下有益效果:
本公开的高温气冷堆堆芯等温温度系数测量方法在具体操作时,高温气冷堆等温温度系数α(T)
上升及高温气冷堆等温温度系数α(T)
下降计算 B℃处高温气冷堆堆芯的等温温度系数,避免高温气冷堆较大热容量缓冲带来的测量误差,从而获得较为准确的等温温度系数。
为了使本技术领域的人员更好地理解本公开方案,下面将结合本公开实施例,对本公开实施例中的技术方案进行清楚、完整地描述,显然,所描述的实施例仅仅是本公开一部分的实施例,不是全部的实施例,而并非要限制本公开公开的范围。此外,在以下说明中,省略了对公知结构和技术的描述,以避免不必要的混淆本公开公开的概念。基于本公开中的实施例,本领域普通技术人员在没有做出创造性劳动前提下所获得的所有其他实施例,都应当属于本公开保护的范围。
本公开的高温气冷堆堆芯等温温度系数测量方法包括以下步骤:
1)将吸收球全部至于反应堆顶部;
2)将控制棒至于临界棒位处;
3)反应堆功率维持在核加热点(POAH点)以下;
4)反应性仪已经投入监测反应性;
5)主氦风机全速稳定运行,一回路加热投入;
6)将一回路加热温度至240℃,停止一回路加热,在该温度下主氦风机的全速稳定运行超过30min后,记录该温度下的反应性;
7)重新投入一回路加热,待一回路温度升高ΔT℃后,停止一回路加热,再保持一回路的温度稳定;
8)等待超过30min后,记录当前温度下的反应性;
9)重复步骤7)至步骤8),直至一回路温度达到260℃为止;
10)绘制一回路温度上升段范围内的温度-反应性拟合曲线,将250℃处温度-反应性拟合曲线的斜率作为高温气冷堆等温温度系数α(T)
上升;
11)主氦风机降频运行,投入水冷壁或者将余热导出系统对一回路进行逐步降温;
12)待一回路温度降低ΔT℃后,切除水冷壁,保持一回路温度稳定;
13)在该温度下保持稳定超过30min后,记录当前温度下的反应性;
14)重复步骤11)至步骤13),直至一回路温度降低至240℃为止;
15)绘制一回路温度下降段范围内的温度-反应性拟合曲线,将250℃处温度-反应性拟合曲线的斜率作为高温气冷堆等温温度系数α(T)
下降;
16)计算差值Δα=α(T)
上升-α(T)
下降;
17)重复步骤5)至步骤16),直至∣Δα∣≤2pcm/℃为止;
18)计算250℃处的等温温度系数α(T),其中,250℃处的等温温度系数为250℃处温度上升段和下降段等温温度系数的平均值,即α(T)=[α(T)
上升+α(T)
下降]/2。
其中,ΔT的取值范围在1~2℃;
需要说明的是,高温气冷堆其他温度下的等温温度系数获取方法类似。
本公开针对高温气冷堆堆芯热容量大、热惯性大的问题,在较大范围内对一回路进行升温,并测量每个温度台阶对应的反应性,获取一定温度范围内的温度—反应性拟合曲线,根据拟合曲线在确定温度处的斜率,得到此温度对应上升沿的等温温度系数。同样进行降温操作,得到此温度下降沿的等温温度系数。循环进行上述操作,直到两者等温温度 系数差值≤2pcm/℃;最终的等温温度系数取上升沿和下降沿等温温度系数的平均值。
Claims (8)
- 一种高温气冷堆堆芯等温温度系数测量方法,其特征在于,包括以下步骤:1)绘制一回路温度上升段范围内的温度-反应性拟合曲线,将B℃处温度-反应性拟合曲线的斜率作为高温气冷堆等温温度系数α(T) 上升;2)绘制一回路温度下降段范围内的温度-反应性拟合曲线,将B℃处温度-反应性拟合曲线的斜率作为高温气冷堆等温温度系数α(T) 下降;3)计算B℃处高温气冷堆堆芯的等温温度系数α(T)=[α(T) 上升+α(T) 下 降]/2。
- 根据权利要求1所述的高温气冷堆堆芯等温温度系数测量方法,其特征在于,具体包括以下步骤:11)进行前期准备工作;12)将一回路加热温度至A℃,停止一回路加热,在该温度下主氦风机的全速稳定运行超过Nmin后,记录该温度下的反应性;13)重新投入一回路加热,待一回路温度升高ΔT℃后,停止一回路加热,再保持一回路的温度稳定;14)等待超过Nmin后,记录当前温度下的反应性;15)重复步骤13)至步骤14),直至一回路温度达到C℃为止;16)绘制一回路温度上升段范围内的温度-反应性拟合曲线,将B℃处温度-反应性拟合曲线的斜率作为高温气冷堆等温温度系数α(T) 上升,其中,A<B<C;17)主氦风机降频运行,对一回路进行逐步降温;18)待一回路温度降低ΔT℃后,切除水冷壁,保持一回路温度稳定;19)在该温度下保持稳定超过Nmin后,记录当前温度下的反应性;110)重复步骤17)至步骤19),直至一回路温度降低至A℃为止;111)绘制一回路温度下降段范围内的温度-反应性拟合曲线,将B℃处温度-反应性拟合曲线的斜率作为高温气冷堆等温温度系数α(T) 下降;112)计算差值Δα=α(T) 上升-α(T) 下降;113)重复步骤11)至步骤112),直至∣Δα∣≤预设值为止;116)计算B℃处高温气冷堆堆芯的等温温度系数α(T)=[α(T) 上升+α(T) 下降]/2。
- 根据权利要求2所述的高温气冷堆堆芯等温温度系数测量方法,其特征在于,B=250;C=260;A=240。
- 根据权利要求2所述的高温气冷堆堆芯等温温度系数测量方法,其特征在于,ΔT的取值范围在1~2℃。
- 根据权利要求2所述的高温气冷堆堆芯等温温度系数测量方法,其特征在于,步骤11)的具体过程为:11a)将吸收球全部至于反应堆顶部;11b)将控制棒至于临界棒位处;11c)反应堆功率维持在核加热点以下;11d)反应性仪已经投入监测反应性;11e)主氦风机全速稳定运行,一回路加热投入。
- 根据权利要求2所述的高温气冷堆堆芯等温温度系数测量方法,其特征在于,步骤17)中,投入水冷壁或者将余热导出系统对一回路进行逐步降温。
- 根据权利要求2所述的高温气冷堆堆芯等温温度系数测量方法,其特征在于,N=30。
- 根据权利要求2所述的高温气冷堆堆芯等温温度系数测量方法,其特征在于,预设值为2pcm/℃。
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Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2014163803A (ja) * | 2013-02-25 | 2014-09-08 | Mitsubishi Heavy Ind Ltd | 反応度温度係数推定装置及び方法 |
CN106782709A (zh) * | 2016-11-25 | 2017-05-31 | 福建福清核电有限公司 | 一种零功率物理试验等温温度系数测量值修正方法 |
CN109741840A (zh) * | 2018-12-26 | 2019-05-10 | 福建福清核电有限公司 | 一种等温温度系数测量的优化方法 |
CN114822888A (zh) * | 2022-05-25 | 2022-07-29 | 西安热工研究院有限公司 | 一种高温气冷堆堆芯等温温度系数测量方法 |
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2022
- 2022-05-25 CN CN202210577096.2A patent/CN114822888A/zh active Pending
- 2022-12-20 WO PCT/CN2022/140296 patent/WO2023226394A1/zh unknown
Patent Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2014163803A (ja) * | 2013-02-25 | 2014-09-08 | Mitsubishi Heavy Ind Ltd | 反応度温度係数推定装置及び方法 |
CN106782709A (zh) * | 2016-11-25 | 2017-05-31 | 福建福清核电有限公司 | 一种零功率物理试验等温温度系数测量值修正方法 |
CN109741840A (zh) * | 2018-12-26 | 2019-05-10 | 福建福清核电有限公司 | 一种等温温度系数测量的优化方法 |
CN114822888A (zh) * | 2022-05-25 | 2022-07-29 | 西安热工研究院有限公司 | 一种高温气冷堆堆芯等温温度系数测量方法 |
Non-Patent Citations (1)
Title |
---|
SHOU-YIN HU, WANG RUI-PIAN, JING XING-QING, LIANG XI-HUA: "Measurement and Evaluation of Temperature Coefficient of 10 MW High Temperature Gas-Cooled Reactor-Test Module", NUCLEAR POWER ENGINEERING, vol. 25, no. 4, 28 August 2004 (2004-08-28), pages 301 - 304, XP093111775 * |
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