JPS6337913B2 - - Google Patents
Info
- Publication number
- JPS6337913B2 JPS6337913B2 JP55032777A JP3277780A JPS6337913B2 JP S6337913 B2 JPS6337913 B2 JP S6337913B2 JP 55032777 A JP55032777 A JP 55032777A JP 3277780 A JP3277780 A JP 3277780A JP S6337913 B2 JPS6337913 B2 JP S6337913B2
- Authority
- JP
- Japan
- Prior art keywords
- radioactivity
- accident
- monitor
- released
- treatment system
- 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.)
- Expired
Links
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 claims description 12
- 239000011630 iodine Substances 0.000 claims description 12
- 229910052740 iodine Inorganic materials 0.000 claims description 12
- 239000000446 fuel Substances 0.000 claims description 11
- 238000012544 monitoring process Methods 0.000 claims description 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 2
- 239000007789 gas Substances 0.000 description 35
- 239000012071 phase Substances 0.000 description 5
- 238000009423 ventilation Methods 0.000 description 4
- 230000005855 radiation Effects 0.000 description 3
- 238000004378 air conditioning Methods 0.000 description 2
- 230000007423 decrease Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000005259 measurement Methods 0.000 description 2
- 230000002159 abnormal effect Effects 0.000 description 1
- 230000008602 contraction Effects 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000007791 liquid phase Substances 0.000 description 1
- 229910052756 noble gas Inorganic materials 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 230000001629 suppression Effects 0.000 description 1
Classifications
-
- 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
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Measurement Of Radiation (AREA)
Description
【発明の詳細な説明】
本発明は、事故拡大予測モニタシステムに係
り、特に非常用ガス処理系に適用するに好適な事
故拡大予測モニタシステムに関するものである。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to an accident expansion prediction monitoring system, and particularly to an accident expansion prediction monitoring system suitable for application to an emergency gas treatment system.
事故時等に、原子炉建屋及び原子炉格納容器内
の機器からの漏洩及び異常放射能を検知した場
合、非常用ガス処理系が作動して漏洩した放射性
ガスは非常用ガス処理系を通して系外へ放出され
る。この系外放出放射能量は、既設の非常用ガス
処理系排気モニタにより監視されている。しか
し、既設のシステムは、周辺住民の避難等の警告
を行える程度の情報を与えることができない。従
つて、事故時の系外放出放射能量を評価するとと
もに、事故拡大の予測を行い、発電所周辺への対
応策を速やかに行うことが望まれている。 In the event of an accident, if leakage or abnormal radioactivity is detected from equipment in the reactor building or reactor containment vessel, the emergency gas treatment system will activate and the leaked radioactive gas will be removed from the system through the emergency gas treatment system. released to. The amount of radioactivity released outside the system is monitored by the existing emergency gas treatment system exhaust monitor. However, existing systems cannot provide enough information to warn nearby residents about evacuation, etc. Therefore, it is desirable to evaluate the amount of radioactivity released outside the system at the time of an accident, predict the spread of the accident, and promptly take countermeasures around the power plant.
本発明の目的は、事故の状態を知ることができ
しかも周辺への影響を容易に予測できる故障拡大
予測システムを提供することにある。 SUMMARY OF THE INVENTION An object of the present invention is to provide a failure expansion prediction system that can determine the state of an accident and easily predict the impact on surrounding areas.
本発明の特徴は、事故時に非常用ガス処理系か
ら放出されるガス中の希ガスの放射能濃度及びよ
う素の放射能濃度の測定を行い、よう素の放射能
濃度に対する希ガスの放射能濃度の比率に基づい
て故障の状態を判別し、放出ガスの放射能濃度の
時間変化率に基づいて故障の拡大を予測すること
にある。 The feature of the present invention is to measure the radioactivity concentration of rare gases and the radioactivity concentration of iodine in the gas released from the emergency gas treatment system in the event of an accident, and to measure the radioactivity concentration of the rare gas relative to the radioactivity concentration of iodine. The objective is to determine the failure state based on the concentration ratio and predict the expansion of the failure based on the time rate of change in the radioactivity concentration of the released gas.
本発明の実施例を図面を用いて以下に説明す
る、
第１図に本実施例の被曝低減を目的とした事故
拡大予測モニタシステムを示す。原子炉格納容器
２が、原子炉建屋１内に配置されている。原子炉
建屋１の換気は、フイルタ５を有する原子炉建屋
換気空調系３にて行われる。６は原子炉建屋排気
放射線モニタである。非常用ガス処理系４は、原
子炉建屋１内に開口し、フイルタ５を経て主排気
筒（図示せず）につながつている。本実施例の事
故拡大予測システムは、非常用ガス処理系４内の
気相中の全放射能を検出するGM管モニタ７、そ
の気相中のよう素による放射能を検出するよう素
モニタ８及びその気相中の希ガスによる放射能を
検出する希ガスモニタ（NaIモニタ）９からなる
非常用ガス処理系モニタ系、この非常用ガス処理
系モニタ系にて連続的に測定された情報（放射能
濃度）に基づいて系外に放出される放射能量の変
化率より事故拡大予測を行うと共に事故の状態を
判別する事故拡大判別装置１０、及び放射能濃度
の時間変化及び事故の状態、すなわち事故拡大判
別装置１０による処理結果を表示する表示装置１
１から構成される。GM管モニタ７、よう素モニ
タ８及び希ガスモニタ９は、非常用ガス処理系４
に設けられる。 An embodiment of the present invention will be described below with reference to the drawings. Fig. 1 shows an accident expansion prediction monitoring system for reducing radiation exposure according to the present embodiment. A reactor containment vessel 2 is arranged within the reactor building 1 . Ventilation of the reactor building 1 is performed by a reactor building ventilation air conditioning system 3 having a filter 5 . 6 is a reactor building exhaust radiation monitor. The emergency gas treatment system 4 opens into the reactor building 1 and is connected to a main exhaust stack (not shown) via a filter 5. The accident expansion prediction system of this embodiment includes a GM tube monitor 7 that detects all radioactivity in the gas phase in the emergency gas treatment system 4, and an iodine monitor 8 that detects radioactivity due to iodine in the gas phase. The emergency gas treatment system monitor system consists of a rare gas monitor (NaI monitor) 9 that detects radioactivity due to the rare gas in the gas phase, and information (radiation) continuously measured by this emergency gas treatment system monitor system. an accident escalation determination device 10 that predicts the escalation of an accident based on the rate of change in the amount of radioactivity released outside the system based on the radioactivity concentration) and determines the state of the accident; and Display device 1 that displays processing results by the magnification discrimination device 10
Consists of 1. The GM tube monitor 7, the iodine monitor 8, and the rare gas monitor 9 are connected to the emergency gas processing system 4.
established in
次に、非常用ガス処理系モニタ系により得られ
る情報に基づいて事故拡大を予測する原理を以下
に説明する。 Next, the principle of predicting the spread of an accident based on the information obtained by the emergency gas processing system monitoring system will be explained below.
非常用ガス処理系モニタ系にて得られる放射能
濃度変化を求めるにあたり下記の様な仮定を行
う。 The following assumptions are made when determining the change in radioactivity concentration obtained by the emergency gas treatment system monitor system.
(1) 原子炉建屋内の放射能濃度と非常用ガス処理
系配管内の放射能濃度は同じとする。ただし、
よう素については非常用ガス処理系４のよう素
フイルタ５による除去があるものとする。(1) The radioactivity concentration inside the reactor building and the radioactivity concentration inside the emergency gas treatment system piping shall be the same. however,
It is assumed that iodine is removed by the iodine filter 5 of the emergency gas treatment system 4.
(2) 簡単のため希ガス全核種の崩壊定数を１つの
崩壊定数で代表する。よう素についても同様と
する。(2) For simplicity, the decay constants of all noble gas nuclides are represented by one decay constant. The same applies to iodine.
(3) 燃料棒より放出される放射能量はQ0Ciとす
る。(3) The amount of radioactivity released from the fuel rods is Q 0 Ci.
上記仮定に基づけば、原子炉格納容器２内の放
射能濃度及び原子炉建屋１内の放射能濃度は下記
のようになる。 Based on the above assumptions, the radioactivity concentration in the reactor containment vessel 2 and the radioactivity concentration in the reactor building 1 are as follows.
(a) 原子炉格納容器２内の放射能濃度
事故時の放射能に関する微分方程式は、次式
のようになる。(a) Radioactivity concentration in reactor containment vessel 2 The differential equation regarding radioactivity at the time of the accident is as follows.
dQPCV／dt＝Q0−λL1F3・QPCV−λRQPCV ……(1)
QPCV＝Q0e-(〓L1+〓R)t ……(2)
ただし、
Q0は燃料棒からの放出率（Ci）、
QPCVは原子炉格納容器２内の気相中の放射能
増加量（Ci）、
λL1は格納容器から原子炉棟への漏洩率
（１／ｄ）、
F3は気相中と液相中の放射能量の比、
及びλRは核種の崩壊定数（１／ｄ）である。 dQ PCV ／dt＝Q 0 −λ L1 F 3・Q PCV −λ R Q PCV ……(1) Q PCV ＝Q 0 e -( 〓 L1+ 〓 R)t ……(2) However, Q 0 is the fuel The release rate from the rod (Ci), Q PCV is the increase in radioactivity in the gas phase in the reactor containment vessel 2 (Ci), λ L1 is the leakage rate from the containment vessel to the reactor building (1/d), F 3 is the ratio of the amount of radioactivity in the gas phase to that in the liquid phase, and λ R is the decay constant (1/d) of the nuclide.
(1)式より原子炉格納容器２内の放射能濃度
QPCVは、次式で表わされる。 From equation (1), the radioactivity concentration in the reactor containment vessel 2
Q PCV is expressed by the following formula.
CPCV＝QPCV／VPCV ……(3)
ここで、VPCVは原子炉格納容器１内の体積
である。 C PCV = Q PCV /V PCV ... (3) Here, V PCV is the volume inside the reactor containment vessel 1.
(b) 原子炉建屋２内の放射能濃度
事故時における放射能に関する微分方程式
は、次式のようになる。(b) Radioactivity concentration in reactor building 2 The differential equation regarding radioactivity at the time of the accident is as follows.
dQR/B／dt＝λL1QPCV−λL2QR/B ……(4)
ここで、QR/Bは原子炉建屋１内の放射能増加
量（Ci／Ｓ）、
λL2は非常用ガス処理系４による原子炉建屋
１内の空気の換気率（１／ｄ）である。 dQ R/B /dt=λ L1 Q PCV −λ L2 Q R/B ...(4) Here, Q R/B is the increase in radioactivity in reactor building 1 (Ci/S), and λ L2 is This is the ventilation rate (1/d) of the air in the reactor building 1 by the emergency gas treatment system 4.
(4)式に(2)式を導入すると、(5)式が得られる。 Introducing equation (2) into equation (4), equation (5) is obtained.
ｄ／dt（QR/B・eλL2ｔ）＝λL1Q0e−（λL1
＋λR＋λL2）ｔ……(5)
(5)式より原子炉建屋１内の放射能濃度QR/B
は、次式のようになる。 d/dt(Q R/B・eλ L2 t)=λ L1 Q 0 e−(λ L1
+λ R +λ L2 ) t...(5) From equation (5), radioactivity concentration Q R/B in reactor building 1
is as follows.
CR/B＝QR/B／VR/B ……(6) ここでVR/Bは原子炉建屋１内の体積である。 C R/B =Q R/B /V R/B (6) Here, V R/B is the volume inside the reactor building 1.
ここで(5)式を整理すると、放射能濃度変化率
ｇは次のようになる。 When formula (5) is rearranged, the radioactivity concentration change rate g is as follows.
ｇ＝ｅ（λL1＋λR＋λL2）ｄｄ／dt（CR/B・eλ
L2ｔ）＝λL1／VR/B・Q0……(7)
従つて、(7)式を用いて以下に示す３つの形態
を認識できる。 g=e(λ L1 +λ R +λ L2 )dd/dt(C R/B・eλ
L2 t)=λ L1 /V R/B ·Q 0 (7) Therefore, the following three forms can be recognized using equation (7).
(1) 定常的に一定の割合で放射能が放出される
場合(7)式は
ｇ＝g0g0＝λL1／VR/B・Q0一定
(2) 一定の割合で燃料から放射能の放出率が増
加する場合
(7)式は
ｇ＝g0＋Kt （Ｋ＞０）
(3) 一定の割合で燃料からの放射能放出率が減
少する場合
(7)式は
ｇ＝g0−Kt Ｋ＞０）
以上の原理より、前述の非常用ガス処理系モ
ニタ系の測定結果により(7)式を求め、放射能濃
度の時間依存性を求める。 (1) When radioactivity is emitted at a constant rate, equation (7) is g = g 0 g 0 = λ L1 /V R/B・Q 0 constant (2) Emitted from the fuel at a constant rate When the radioactivity release rate increases, equation (7) is g=g 0 +Kt (K>0) (3) When the radioactivity release rate from fuel decreases at a constant rate, equation (7) becomes g=g 0 -Kt K>0) Based on the above principle, equation (7) is obtained from the measurement results of the emergency gas processing system monitor system mentioned above, and the time dependence of the radioactivity concentration is obtained.
前述の３つの形態の例を第２図、第３図及び第
４図に示す。第２図は燃料棒から一定の割合で放
出される場合を示し、第３図は燃料棒から時間と
ともに増加する割合で放出されていることから事
故が拡大していることを示し、第４図は事故が縮
小していることを示す。 Examples of the three aforementioned configurations are shown in FIGS. 2, 3, and 4. Figure 2 shows the case where the fuel is released from the fuel rod at a constant rate, Figure 3 shows that the accident is expanding as the fuel is released from the fuel rod at a rate that increases over time, and Figure 4 shows that the accident is expanding. indicates that accidents are decreasing.
本実施例によれば、非常用ガス処理系モニタ系
の各モニタによる放射能の連続計測を行い、事故
拡大判別装置１０による各モニタの計測結果に基
づいた前述の放射能濃度変化率ｇの傾向の認識に
より
１ 定常的に放射能が放出される場合、
２ 事故が拡大し、放出放射能の増加が予測され
る場合、及び
３ 事故が縮小傾向にあると予測される場合
の事故拡大予測が容易に行える。 According to this embodiment, radioactivity is continuously measured by each monitor of the emergency gas treatment system monitor system, and the trend of the radioactivity concentration change rate g described above is based on the measurement results of each monitor by the accident escalation determination device 10. By recognizing that 1. radioactivity is steadily released, 2. the accident is expanding and the released radioactivity is expected to increase, and 3. the accident is predicted to be on the decline. It's easy to do.
また、事故拡大判別装置１０は、希ガス及びよ
う素の放射能濃度比α（＝（希ガスの放射能濃度
度）／（よう素の放射能濃度））により、下記の
(i)及び(ii)の事故状態を判別する。 In addition, the accident escalation determination device 10 uses the radioactivity concentration ratio α of rare gas and iodine (=(radioactivity concentration of rare gas)/(radioactivity concentration of iodine)) to determine the following:
Determine the accident conditions of (i) and (ii).
(i) 炉水がサプレツシヨンチエンバーに放出され
た場合：α＜１
(ii) 燃料破損が生じている場合：α＞１
このように本発明によれば、事故状態を判別で
きしかも事故の拡大・縮少を予測でき、周辺住民
への被曝の拡大等の影響を容易に知ることができ
る。(i) When reactor water is released into the suppression chamber: α < 1 (ii) When fuel damage occurs: α > 1 As described above, according to the present invention, it is possible to determine the accident state and also prevent the accident from occurring. It is possible to predict the expansion or contraction of radiation exposure, and to easily understand the effects of expansion of radiation exposure on surrounding residents.
第１図は本発明の一実施例の系統図、第２図、
第３図及び第４図は非常用ガス処理系モニタ系の
測定値に基づく三つの形態を示す説明図である。
１……原子炉建屋、２……原子炉格納容器、３
……原子炉建屋換気空調系、４……非常用ガス処
理系、５……フイルタ、６……原子炉建屋排気放
射線モニタ、７……GM管モニタ、８……よう素
モニタ、９……希ガスモニタ、１０……事故拡大
判別装置、１１……表示装置。
FIG. 1 is a system diagram of an embodiment of the present invention, FIG.
FIGS. 3 and 4 are explanatory diagrams showing three forms based on measured values of the emergency gas processing system monitor system. 1...Reactor building, 2...Reactor containment vessel, 3
... Reactor building ventilation air conditioning system, 4 ... Emergency gas treatment system, 5 ... Filter, 6 ... Reactor building exhaust radiation monitor, 7 ... GM pipe monitor, 8 ... Iodine monitor, 9 ... Rare gas monitor, 10... Accident expansion determination device, 11... Display device.
Claims (1)
ス処理系にて放出されるガス中のよう素の放射能
濃度を検出する第１放射能モニタと、前記非常用
ガス処理系に設けられて前記放出ガス中の希ガス
の放射能濃度を検出する第２放射能モニタと、前
記第１放射能モニタの測定値に対する前記第２放
射能モニタの測定値の比率に基づいて炉水が圧力
抑制室に放出された事故か燃料破損が生じた事故
かを判別し、前記第１及び第２放射能モニタにて
測定された放射能濃度の時間変化率に基づいて事
故の拡大を予測する手段とを備えた事故拡大予測
モニタシステム。1. A first radioactivity monitor installed in the emergency gas treatment system to detect the radioactivity concentration of iodine in the gas released by the emergency gas treatment system; A second radioactivity monitor detects the radioactivity concentration of the rare gas in the released gas, and the pressure of the reactor water is suppressed based on the ratio of the measured value of the second radioactivity monitor to the measured value of the first radioactivity monitor. means for determining whether the accident is an accident in which fuel was released into the room or an accident in which fuel was damaged, and predicting the expansion of the accident based on the time rate of change in the radioactivity concentration measured by the first and second radioactivity monitors; Accident expansion prediction monitoring system equipped with
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP3277780A JPS56129892A (en) | 1980-03-17 | 1980-03-17 | Monitor system of accident extension forcasting for exposure effect |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP3277780A JPS56129892A (en) | 1980-03-17 | 1980-03-17 | Monitor system of accident extension forcasting for exposure effect |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS56129892A JPS56129892A (en) | 1981-10-12 |
| JPS6337913B2 true JPS6337913B2 (en) | 1988-07-27 |
Family
ID=12368265
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP3277780A Granted JPS56129892A (en) | 1980-03-17 | 1980-03-17 | Monitor system of accident extension forcasting for exposure effect |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS56129892A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2922667A1 (en) * | 2007-10-22 | 2009-04-24 | Commissariat Energie Atomique | METHOD FOR MANAGING A TIME-EVOLVING ACCIDENT |
-
1980
- 1980-03-17 JP JP3277780A patent/JPS56129892A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS56129892A (en) | 1981-10-12 |
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