【発明の詳細な説明】本発明は、高速増殖炉運転監視に係り、特に炉内異常に
よる微小な燃料集合体出口冷却材温度上昇を早期に検出
し、１！！蔽員に警・服を発し、ｊｔ大事故を未然に防
止ｒる高速炉炉心異常監視＠置に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to fast breeder reactor operation monitoring, and in particular, detects at an early stage a minute rise in the temperature of the coolant at the exit of a fuel assembly due to an abnormality in the reactor. ! Regarding monitoring of abnormalities in the fast reactor core to prevent serious accidents by alerting personnel and preventing major accidents.
高速炉の燃料棒はラッパー管内を正三角形犬に高密度に
配列して収納された・燃料集合体で構成され、燃料集合
体内に計測器を設置べｒることが困・碓であるへ、通常
は集合体上部の計装ウェルに温度計や流Ｉ計が設置され
ている。従って、燃料集合体内で部分流路閉塞など異常
事象が元生した場合、閉塞した近傍は冷却材温度が高温
になるが、冷却材が集合体上部の出口まで到達するまで
に平坦化Ｎれ、その偲１度上昇は微小であろう一方、原
子炉の１山常１車転中の出力変動や原子炉人口冷却材流
量、温度変化による燃料集合体出口温度変化もあり、前
記異常温度変化を燃料集合休出１」温度計のみでｔ！ｉ
＋、＃に・検出することは困難であつｔ、。The fuel rods of a fast reactor consist of fuel assemblies arranged densely in an equilateral triangular shape inside the wrapper tube, and it is difficult and difficult to install measuring instruments inside the fuel assemblies. Usually, a thermometer and a flow I meter are installed in the instrumentation well at the top of the assembly. Therefore, when an abnormal event such as a partial flow passage blockage occurs in a fuel assembly, the coolant temperature becomes high near the blockage, but the coolant flattens out by the time it reaches the outlet at the top of the assembly. While the 1 degree increase would be small, there are also changes in the fuel assembly outlet temperature due to power fluctuations during one rotation of the reactor, the reactor artificial coolant flow rate, and temperature changes, and the above abnormal temperature change Fuel assembly break 1” Only with a thermometer! i
+, #, and difficult to detect.
本発明の目的は、上νｆの問題点を鑑み、通常運転中の
燃料集合体出口温度変化と炉内異常原因による燃料集合
休出ロイ゛昌度変化をデータ演げ処理装置ｒｉで計；１
し、イｎ兜よく分離し、真の異常温度変化のみを倹知す
る高速炉炉心異常監睨装置を提供することにある。In view of the above problem of νf, an object of the present invention is to calculate, using a data processing device ri, changes in fuel assembly outlet temperature during normal operation and changes in fuel assembly shutoff temperature due to abnormalities in the reactor;
However, it is an object of the present invention to provide a fast reactor core abnormality monitoring device that can separate the internal components well and know only the true abnormal temperature changes.
この目的を４成するため、本発明は、原子炉が正常な状
峠で運転されている１募合の燃料集合体出口温度変化に
起因するものを以上に説明する５つの要素に分析できる
ことに着目し、各要素の正常時の温度変化最の和と燃料
集合体出口温度計で計測された温度変化の差１５工ら異
常温度変化を算出する。ここで、５つの要素とは、（１
）炉心熱出力変動による燃料集合体出口温度変化、（２
）炉心入口冷却材流量変動による燃料集合体出口温度変
化、（３）炉心入口冷却材温度変動による燃料集合体出
口温度変化、（４）制御棒挿入敞１好変史による・燃料
集合体出口温度変化、（５）燃料燃焼に伴う燃料集合体
出口温度変化であるつ以下、本発明の一実施例を第１図により説明する。１は
原子炉、２は各燃料集合体上部に設置される冷却材温度
計、３は炉容器外に設置される中性子束計装装置で、炉
心熱出力算出に使用する。In order to achieve this objective, the present invention is based on the fact that what is caused by the temperature change at the exit of a fuel assembly when a nuclear reactor is operated under normal conditions can be analyzed into the five factors explained above. Focusing on this, the abnormal temperature change is calculated from the difference of 15 degrees between the sum of the normal temperature changes of each element and the temperature change measured by the fuel assembly outlet thermometer. Here, the five elements are (1
) Fuel assembly outlet temperature change due to core thermal output fluctuation, (2
) Fuel assembly outlet temperature change due to core inlet coolant flow rate fluctuation, (3) Fuel assembly outlet temperature change due to core inlet coolant temperature change, (4) Fuel assembly outlet temperature due to control rod insertion history. (5) Change in fuel assembly outlet temperature due to fuel combustion.An embodiment of the present invention will now be described with reference to FIG. 1 is a nuclear reactor, 2 is a coolant thermometer installed at the top of each fuel assembly, and 3 is a neutron flux instrumentation device installed outside the reactor vessel, which is used to calculate the reactor core thermal output.
４は炉心内に流入する冷却材の流−計、５は炉心内に流
入する冷却材の温度計、６け制御棒挿入位１ｄ検出＠看
。以上は通常の高速増殖炉に設置される炉内計装設備で
ある。こノ１ら２から６の計装信号データを７のデータ
演算灰理装置角に取込む。4 is a flow meter for the coolant flowing into the reactor core, 5 is a thermometer for the coolant flowing into the core, and 6 is a control rod insertion position 1d detection @ observation. The above is the in-core instrumentation equipment installed in a normal fast breeder reactor. The instrumentation signal data from 1 and 2 to 6 is taken into the data calculation analyzer angle 7.
具体的には、３の炉心熱出力、４の炉心入口流量、５の
炉心入口温度、６の制御卸Ｓ位置の計装信号データを取
込み、８の偏差算出装置葭により、時刻ｔ。と時ａｌｌ
ｔ＋の時間変化における各計装信号データの偏差を求
める９次に８で求まった各偏差ノーーータを屑に燃料集
会休出口・熱度変化を９の温度変化ｔ￥出装（ｉ（によ
り求めると同時に、燃料燃焼による燃料集合体出口温度
変化をＭＦ ’ｌ−１３干る、一方、２の各燃料集会休
出口招度計の計装信号データを１（）の出口昌鵡を計変
化婢、出装肯に取込み、９で求まった温度変化を１！の
幅用“変化比較装置ａにより差を求め、〕・め設定され
た倫度変化範囲土ε、を越えた場合、１２の警服装）ｄ
により警報を発すと同時に、１３のＣＲＴ表示表示前１
４り昼常となった原因刊１す１資料を表示するう犬に：ｊｆＪ記、データ演算処叩装閘で計ｑする内容に
ついて説明する。今、原子炉が運転されている時の各・
燃料集合体出口温度計化Δ’、［’Ｋ ｌは次式で表わ
される。Specifically, the instrumentation signal data of the core thermal output (3), the core inlet flow rate (4), the core inlet temperature (5), and the control outlet S position (6) are taken in, and the deviation calculation device (8) calculates the time t. and time all
Calculate the deviation of each instrumentation signal data with respect to the time change of t+ 9 Next, use each deviation node found in 8 as waste and calculate the temperature change in 9, t\output (i), and at the same time , the temperature change at the outlet of the fuel assembly due to fuel combustion is expressed as MF'l-13, and on the other hand, the instrumentation signal data of each fuel assembly exit indicator in 2 is changed to the exit change in 1(), Incorporate the temperature change found in step 9 into the temperature change range of 1! and calculate the difference using the change comparison device a, and if it exceeds the set ethical change range ε, then the temperature change in step 12 will be applied. d
At the same time as the alarm is issued, the CRT display of 13
4. The reason why it became a daily routine Publication 1 1 To the dog that displays the material: JFJ, I will explain the contents to be calculated in the data calculation department. Currently, each time a nuclear reactor is operating,
The fuel assembly outlet temperature measurement Δ', ['Kl is expressed by the following formula.
ΔＴＭＩ ＝ ｌ Ｔ （−’−（ΔＴＰｌ牛Δ’ｒＦ
ｌ＋ΔＴ＋％−ΔＴｙＢ牛ΔＴＢＩ）ここで、ΔＴ、１：燃料集合燃料集合体出口温度計化ΔＴ■：炉
心異常事象による異常温度変化ΔＴｐ＋ ：炉心熱出
力変＠にょる燃料集合体出口温度変化ΔＴｒ＋ ：炉心人口温度変動による燃料集合体出口
温度変化ΔＴｌｕ ：炉心人口温度変動による燃料集合体出口
温度変化ΔＴＲＩ ：制御棒挿入位置変更による納料集合体出
口搗関変化ΔＴＢ＋：＠料燃焼に伴う燃料集合体出口温度変化従って、炉内異常車蒙による異常温度変化ΔＴ＋は、次
式で求められる。ΔTMI = l T (-'-(ΔTPl cow Δ'rF
l+ΔT+%−ΔTyB (ΔTBI) Here, ΔT, 1: Fuel assembly fuel assembly outlet temperature measurement ΔT■: Abnormal temperature change due to core abnormal event ΔTp+: Core thermal output change @ fuel assembly outlet temperature change ΔTr+: Fuel assembly outlet temperature change due to core population temperature fluctuation ΔTlu: Fuel assembly outlet temperature change due to core population temperature fluctuation ΔTRI: Fuel assembly exit temperature change due to change in control rod insertion position ΔTB+: @Fuel assembly due to fuel combustion Outlet temperature change Therefore, the abnormal temperature change ΔT+ due to the abnormal temperature inside the furnace is determined by the following equation.
ΔＴ＋＝Δ１゛□−（ΔＴＰｌ＋ΔＴＦ＋よΔＴ１よΔ
’Ｉｆ”Ｒ１−Ｊ−Δ’ｒＲ，）今、炉心が正常な場合
、上式の右辺の項は零となり、従って、Δ′ＰＬは零の
値となる。、また、炉内異常の場合は、上式の右辺の項
の平衡が崩れ、異常温度変化Δ］゛１に有音な値となっ
て検知されることにな２）。ΔT+=Δ1゛□−(ΔTPl+ΔTF+yoΔT1→Δ
'If'R1-J-Δ'rR,) Now, if the reactor core is normal, the term on the right side of the above equation is zero, and therefore, Δ'PL has a value of zero. Also, in the case of an abnormality inside the reactor , the balance of the term on the right side of the above equation is disrupted, and the abnormal temperature change Δ]゛1 becomes a loud value and is detected2).
以上述べたように、本発明は、炉心が正常な場合、温度
変化の千両が１呆たれると云う原理に基づぺ、微小な異
常温度変化を検知できる特徴を持っている。As described above, the present invention has the feature that it is possible to detect minute abnormal temperature changes based on the principle that when the reactor core is normal, the temperature change is equal to 1,000 ryo.
高速増殖炉の代表的炉心にｋいてニー１、炉心入口冷却
材渦電は約４００°（：、燃料集合体出口温度計度は約
６５’Ｏｕ（′、橿１ぎで運転され、そのｓ度差約＋５
００Ｃけ・１（竹科の発熱による上＃７分である。In a typical core of a fast breeder reactor, the core inlet coolant eddy current is approximately 400°, the temperature gauge at the exit of the fuel assembly is approximately 65° Degree difference approximately +5
00Cke・1 (upper #7 minutes due to bamboo fever.
一方、燃料も合体内の炉心軸方向中心近くで、約４０％
の冷却材流１洛閉塞事故が宅生してと仮定しｒｒ−！４
分、解析−Ｃけ、閉塞した近傍で冷却材が約ｓｏ（’ｌ
ＯＣ程度旧昇するガ、燃料集会休出口の冷却材温度計契
はたかだか７・Ｃ：冊、変である、つまり、炉心出入１
−］現照度差５０ｏＣに対し約５係惺変の温度上昇とな
る。On the other hand, about 40% of the fuel remains near the axial center of the core within the coalescence.
Assuming that the coolant flow 1 blockage accident occurred in the building, rr-! 4
Minutes, analysis-C, the coolant is about so('l) near the blockage.
The temperature of the coolant temperature gauge at the fuel assembly shut-off port is at most 7.
-] The temperature rises by about 5% relative to the current illuminance difference of 50oC.
次に、原子炉の通常運転時の（？ｔ ６！ｒ ’Ａ″・
１ｄ）や、炉心人口防噴、温＋＆ｉ変化、１ｔｔｌｌ
（＋ｌＵ ４１！位：６賓更などにより約１０チ桿度の
燃料集合休出［１篇度変化が考えられるので、膜常によ
る温ＩＷ変化を１：１（１１つてしまい、燃料集合体出
口温度計のみで異常温度変化を検知することは困難であ
ろう本発明によれば、通常運転中の・燃料集合体出口温度計
化を約２５８Ｃ以内の精度で算出することができ、温度
計が持つゆらき゛約０．５°Ｃを考慮しても約３℃以内
の１度で求められ、異常温度変化の絶対値１ΔＴｅｌの
許容設定節回ε、を３°Ｃ程度にすることができる、従
って、も１７．１Δ’ｒ＋ｌ＞εＴ（＝３°Ｃ）を越えた場合
、警報を−ｉ＠することができる。Next, during normal operation of the nuclear reactor (?t 6!r 'A''・
1d), core artificial blowout prevention, temperature + & i change, 1ttll
(+lU 41st place: The fuel assembly is closed for about 10 degrees due to the change of 6 guests etc. [Since it is possible that the temperature changes by 1 hour, the temperature IW change due to membrane normality will be 1:1 (11 times), and the fuel assembly exit It would be difficult to detect abnormal temperature changes with only a thermometer, but according to the present invention, the temperature at the exit of the fuel assembly during normal operation can be calculated with an accuracy of within about 258C. Even considering the fluctuation of about 0.5°C, it can be determined within 1 degree of about 3°C, and the allowable setting node ε for the absolute value of abnormal temperature change 1ΔTel can be set to about 3°C. If , also exceeds 17.1Δ'r+l>εT (=3°C), an alarm can be set to -i@.
以上のことから、冷却材流路閉塞事故を相定した場合で
も、４０チ閉塞に至る前で検知することができ、冷却材
沸騰による重大事故を未然に防ぐことカニ可能となる、From the above, even if a coolant flow path blockage accident is determined, it can be detected before 40 channels become blocked, making it possible to prevent serious accidents due to coolant boiling.
第１図は本発明の一実施１テリを示すブロック図であり
、原子炉炉内計装設置からのプロセスデータの流れとデ
ータ演算処理装置の機能ブロック図を示したものである
。FIG. 1 is a block diagram showing one embodiment of the present invention, and shows the flow of process data from the installation of instrumentation in a nuclear reactor and a functional block diagram of a data processing device.
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57132213AJPS5923293A (en) | 1982-07-30 | 1982-07-30 | Fast reactor core abnormality monitoring device |
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57132213AJPS5923293A (en) | 1982-07-30 | 1982-07-30 | Fast reactor core abnormality monitoring device |
| Publication Number | Publication Date |
|---|---|
| JPS5923293Atrue JPS5923293A (en) | 1984-02-06 |
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP57132213APendingJPS5923293A (en) | 1982-07-30 | 1982-07-30 | Fast reactor core abnormality monitoring device |
| Country | Link |
|---|---|
| JP (1) | JPS5923293A (en) |
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4655767A (en)* | 1984-10-29 | 1987-04-07 | Dow Corning Corporation | Transdermal drug delivery devices with amine-resistant silicone adhesives |
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS4973597A (en)* | 1972-11-22 | 1974-07-16 |
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS4973597A (en)* | 1972-11-22 | 1974-07-16 |
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4655767A (en)* | 1984-10-29 | 1987-04-07 | Dow Corning Corporation | Transdermal drug delivery devices with amine-resistant silicone adhesives |
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