JPS59126294A - Relaxation device for horizontal pipe temperature distribution of fast breeder - Google Patents
Relaxation device for horizontal pipe temperature distribution of fast breederInfo
- Publication number
- JPS59126294A JPS59126294A JP58000987A JP98783A JPS59126294A JP S59126294 A JPS59126294 A JP S59126294A JP 58000987 A JP58000987 A JP 58000987A JP 98783 A JP98783 A JP 98783A JP S59126294 A JPS59126294 A JP S59126294A
- Authority
- JP
- Japan
- Prior art keywords
- temperature
- liquid metal
- piping
- reactor
- horizontal pipe
- 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.)
- Pending
Links
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
Landscapes
- Pipeline Systems (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
[発明の技術分野]
本発明はρj速増殖炉の水平配管温1度分布緩和装置に
関する。DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a horizontal pipe temperature 1 degree distribution relaxation device for a ρj fast breeder reactor.
[発明の技術的青貝]
第1図は液体金属冷却形高速増殖炉を示すもので、図に
おいて符号1は原子炉容器を示している。[Technical Summary of the Invention] FIG. 1 shows a liquid metal cooled fast breeder reactor, and in the figure, reference numeral 1 indicates a reactor vessel.
この原子炉容器1内には炉心支持板2に支持される炉心
3が配設されている。原子炉容器1の上端開口部には固
定プラグ4が挿入されており、この固定プラグ4に穿設
された貫通孔には、回転プラグ5が挿入されている。こ
の回転プラグ5には偏心して貫通孔が穿設されており、
この貫通孔には炉心上部供構6が挿入されている。原子
炉容器1の下部側面には炉容器入口ノズル配管7が開口
しており、上部側面には炉容器出口ノズル配管8が開口
している。A reactor core 3 supported by a core support plate 2 is disposed within the reactor vessel 1 . A fixed plug 4 is inserted into the upper opening of the reactor vessel 1, and a rotary plug 5 is inserted into a through hole formed in the fixed plug 4. This rotary plug 5 has an eccentric through hole bored therein.
A core upper structure 6 is inserted into this through hole. A reactor vessel inlet nozzle pipe 7 is opened at the lower side of the reactor vessel 1, and a reactor vessel outlet nozzle pipe 8 is opened at the upper side.
以上のように構成された液体金属冷却形高速増殖炉では
、原子炉容器1内には、例えば液体金属ナトリウムから
なる液体金B9か収容されており、原子炉容器1内に炉
容器入口ノズル配管7から流入した比較的低温の液体金
属9は、炉心3で核***による熱エネルギを得た後、炉
容器出口ノズル配管8から流出する。In the liquid metal cooled fast breeder reactor configured as described above, the reactor vessel 1 contains liquid gold B9 made of, for example, liquid metal sodium, and the reactor vessel 1 includes reactor vessel inlet nozzle piping. The relatively low temperature liquid metal 9 flowing in from the reactor core 3 obtains thermal energy through nuclear fission, and then flows out from the reactor vessel outlet nozzle pipe 8.
[背景技術の問題点]
しかしながら、以上のように構成された液体金属冷却形
高速増殖炉では、例えば原子炉がトリップされた場合に
は、炉上部ブレナムの液体金属は、第1図に破線aで示
すように、液体金属の温度差による密度の違いによりホ
ットな上部領域すとコールドな下部領域Cとに二分され
、その間の浮力の差により両者は混合することなく層状
をなし、この層状の状態で炉容器出口ノズル配管8等の
いわゆるホットレグ配管中を流出する。[Problems with the Background Art] However, in the liquid metal cooled fast breeder reactor configured as described above, if the reactor is tripped, for example, the liquid metal in the upper reactor blennium will flow as indicated by the broken line a in FIG. As shown in Figure 2, due to the difference in density caused by the temperature difference in the liquid metal, the liquid metal is divided into a hot upper region and a cold lower region C, and due to the difference in buoyancy between them, the two form a layer without mixing, and this layered In this state, it flows out through the so-called hot leg piping, such as the furnace vessel outlet nozzle piping 8.
すなわち一般に、原子炉のトリップ後は冷却材流量はポ
ニーモータ運転によって供給されるので、定格時の約1
0%となるが、ホットレグ配管内流速も約10%となり
、炉上部ブレナムの体積の大きさも考え合せるとかなり
の長時間に渡り層状をなす液体金属が炉容器出口ノズル
配管8等のホットレグ配管に流入することとなる。そし
てこのような場合には、ホットレグ配管の周方向に沿っ
て不均一な温度分布が生じ、ホットレグ配管を損傷する
おそれがある。That is, generally after a reactor trip, the coolant flow rate is supplied by pony motor operation, so that the rated flow rate is approximately 1
0%, but the flow velocity in the hot leg piping is also about 10%, and considering the volume of the upper furnace brenum, the liquid metal that forms a layer for a considerable period of time enters the hot leg piping such as the furnace vessel outlet nozzle piping 8. There will be an influx. In such a case, non-uniform temperature distribution occurs along the circumferential direction of the hot leg piping, which may damage the hot leg piping.
づなわち例えば、発電用高速炉は冷却材の定格状態とし
て、炉出口温度は530℃、炉入口温度は約400°C
程度であり、冷却系の配管や機器には、例えばステンレ
ス鋼が使われている。しかしながら、このステンレス鋼
のクリープ発生下限は425°Cであり、ホラ1〜レグ
配管や機器はクリープ発生温度領域内で使用されること
となり、このようなホットレグ配管や機器ではクリープ
の発生と、その進行を防止するため引張り、圧縮、剪断
、残留等の各応力を極力排除するとともに、これらの応
力を生ずる原因、例えば熱衝撃等を極力排除することが
要求されている。For example, in a power-generating fast reactor, the temperature at the furnace outlet is 530°C and the temperature at the furnace inlet is approximately 400°C, assuming the coolant is in the rated state.
For example, stainless steel is used for cooling system piping and equipment. However, the lower limit of creep occurrence for stainless steel is 425°C, and hot leg piping and equipment are used within the temperature range where creep occurs. In order to prevent progression, it is required to eliminate tensile, compressive, shearing, residual, and other stresses as much as possible, as well as to eliminate as much as possible the causes of these stresses, such as thermal shock.
[発明の目的]
本発明はかかる従来の事情に対処してなされたもので、
原子炉のトリップ時における液体金属の層化現象に起因
するホットレグ配管の周方向不均一温度分布をなくし、
ホットレグ配管の健会性を 。[Object of the invention] The present invention has been made in response to such conventional circumstances,
Eliminate non-uniform temperature distribution in the circumferential direction of hot leg piping caused by the layering phenomenon of liquid metal during a nuclear reactor trip.
The health of hot leg piping.
維持することのできる高速増殖炉の水平配管温度分布緩
和装置を提供しようとするものである。The present invention aims to provide a horizontal piping temperature distribution relaxation device for a fast breeder reactor that can be maintained.
[発明の概要]
すなわち本発明は、原子炉容器内に液体金属を循環させ
る1次液体金属系の水平配管の上部を冷却する冷却手段
と、前記水平配管の上部および下部の温度をそれぞれ測
定する温度計測手段と、これらの帽U1測手段から前記
水平配管の上部および下部の温度をそれぞれ示す温度信
号を入力し、両者の差が予め定められた一定値を越えた
時に前記冷却手段を作動する液体金属温度制御装置とか
らなることを特徴とする高速増殖炉の水平配管温度分布
緩和装置Cある。[Summary of the Invention] That is, the present invention provides a cooling means for cooling the upper part of a horizontal pipe of a primary liquid metal system that circulates liquid metal in a nuclear reactor vessel, and a cooling means that measures the temperature of the upper and lower parts of the horizontal pipe, respectively. Temperature signals indicating the temperatures at the upper and lower portions of the horizontal pipe are inputted from the temperature measuring means and the cap U1 measuring means, respectively, and when the difference between the two exceeds a predetermined constant value, the cooling means is activated. There is a horizontal piping temperature distribution relaxation device C for a fast breeder reactor, which is characterized by comprising a liquid metal temperature control device.
[発明の実施例1
以下本発明の詳細を図面に示す一実施例について説明す
る。[Embodiment 1 of the Invention] The details of the present invention will be described below with reference to an embodiment shown in the drawings.
第2図は液体金属冷却形高速増殖炉の1次液体金属系を
示すもので、図において符号20は1次液体金属系を示
している。この1次液体金属系20は原子炉で発生した
核エネルギを液体金属を介して中間熱交換器21に移送
するために設けられており、原子炉に液体金属を循環さ
せる1次系配管22には、上流から順に1次系ポンプ2
3、中間熱交換器21、逆止弁24が設けられている。FIG. 2 shows the primary liquid metal system of a liquid metal cooled fast breeder reactor, and in the figure, reference numeral 20 indicates the primary liquid metal system. This primary liquid metal system 20 is provided to transfer the nuclear energy generated in the reactor to the intermediate heat exchanger 21 via liquid metal, and is connected to the primary system piping 22 that circulates the liquid metal in the reactor. are the primary system pump 2 in order from the upstream.
3. An intermediate heat exchanger 21 and a check valve 24 are provided.
そして原子炉容器1と1次系ポンプ23との間は、この
図の例の場合2本の水平配管25.26と2本の垂直配
管27.28とからなるボットレグ配管により接続され
ており、1次系ポンプ23と中間熱交換器21との間は
、この図の例の場合2不の水平配管29.30と2本の
垂直配管31.32とからなるホットレグ配管により接
続されている。In the example shown in this figure, the reactor vessel 1 and the primary system pump 23 are connected by Botleg piping consisting of two horizontal piping 25.26 and two vertical piping 27.28. In the example shown in this figure, the primary system pump 23 and the intermediate heat exchanger 21 are connected by hot leg piping consisting of two horizontal piping 29, 30 and two vertical piping 31, 32.
第3図および第4図は第2図に示す水平配管25.26
.29.30のうち水平配管25を示すもので、図にお
いて符号25は水平配管を示している。Figures 3 and 4 are horizontal piping 25.26 shown in Figure 2.
.. 29.30 shows the horizontal piping 25, and in the figure, the reference numeral 25 indicates the horizontal piping.
この水平配管25を凹稜して保温材33が配設されてあ
り、水平配管25の上部近傍には保温材33を貫通して
水平配管25とほぼ平行に開閉弁34を備えた冷却配管
35が配設されている。水平配管25の上部および下部
の外周に接してそれぞれ温度計からなる温度計測手段3
6.37が配設されており、水平配管25の上部に配設
される温度計測手段36は冷却配管35と温度的に隔離
されている。A heat insulator 33 is disposed along the concave edge of the horizontal pipe 25, and near the top of the horizontal pipe 25, a cooling pipe 35 is provided with an on-off valve 34 that penetrates the heat insulator 33 and runs approximately parallel to the horizontal pipe 25. is installed. Temperature measurement means 3 each consisting of a thermometer are in contact with the outer periphery of the upper and lower parts of the horizontal pipe 25.
6.37 is provided, and the temperature measuring means 36 provided above the horizontal pipe 25 is thermally isolated from the cooling pipe 35.
第3図において符号38は液体金属温度制御装置を示し
ており、この液体金属温度制御装置38は水平配管25
の上部および下部に配設される温度計測手段36.37
からそれぞれ温度信号S1、S2を入力し、この両者の
差が予めこの液体金属温度制御装置3B内に設定された
一定値を越えた時に冷却配管35に配設される開閉弁3
4を開とし冷却配管35内に冷媒を流通する。In FIG. 3, reference numeral 38 indicates a liquid metal temperature control device, and this liquid metal temperature control device 38 is connected to the horizontal pipe 25.
Temperature measuring means 36.37 arranged at the upper and lower parts of the
Temperature signals S1 and S2 are respectively inputted from the temperature signals S1 and S2, and when the difference between the two exceeds a certain value set in advance in this liquid metal temperature control device 3B, the on-off valve 3 disposed in the cooling pipe 35 is activated.
4 is opened to allow the refrigerant to flow into the cooling pipe 35.
なお、液体金属温度制御装置38に予め設定される一定
値は水平配管25内の層化覗象発生時における水平配管
25の上部、配管温度および下部配管温度の温度差にば
は等しく決められている。Note that the constant value preset in the liquid metal temperature control device 38 is determined to be equal to the temperature difference between the upper, pipe temperature, and lower pipe temperature of the horizontal pipe 25 when a stratification phenomenon occurs in the horizontal pipe 25. There is.
以上のように構成された水平配管25では、原子炉のト
リップ時には原子炉容器1内の液体金属の層化現象によ
り第3図に示すように、水平画己管25の下部側には符
号dで示すように低温の液体金属が、水平配管25の上
部側には符号eで示すように、高温の液体金属が層状を
なして流入することとなるが、この低温の液体金属dの
温度と高温の液体金属eの温度とは常に温度計測手段3
6.37により測定されており、層化現象の発生により
この両者の差が予め定められた一定値を越えた時に液体
金属温度制御装置38により冷却配管35の開閉弁34
が開とされ、冷却配管35内に冷却媒体が流通される。In the horizontal pipe 25 configured as described above, when the reactor trips, due to the stratification phenomenon of the liquid metal in the reactor vessel 1, as shown in FIG. The low-temperature liquid metal flows into the upper side of the horizontal pipe 25 in a layered manner as shown by the symbol e, but the temperature of the low-temperature liquid metal d and The temperature of the high-temperature liquid metal e is always measured by the temperature measuring means 3.
6.37, and when the difference between the two exceeds a predetermined constant value due to the occurrence of the stratification phenomenon, the liquid metal temperature control device 38 turns on/off the opening/closing valve 34 of the cooling pipe 35.
is opened, and the cooling medium flows through the cooling pipe 35.
従って、層化現象により水平配管25の上部を流れる高
温の液体金属eは冷却配管35内を流通する冷媒により
冷却され、温度が低下し水平配管25の下部側を流れる
低温の液体金属dとほぼ同じ温度まで冷却され、従来、
水平配管25等のホットレグ配管に発生していた周方向
の不均一湿度分布を完全に解消することができ、この下
流側に配設される各種機器、配管等に与える熱衝撃を大
幅に軽減することができる。Therefore, the high-temperature liquid metal e flowing in the upper part of the horizontal pipe 25 due to the stratification phenomenon is cooled by the refrigerant flowing in the cooling pipe 35, and its temperature decreases to almost the same as the low-temperature liquid metal d flowing in the lower part of the horizontal pipe 25. Traditionally, it is cooled to the same temperature.
The non-uniform humidity distribution in the circumferential direction that occurs in hot leg piping such as the horizontal piping 25 can be completely eliminated, and the thermal shock given to various equipment, piping, etc. installed downstream of this piping can be significantly reduced. be able to.
なお、水平配管25の上部および下部を流れる液体金属
の温度がほぼ等しくなった場合には、温度計測手段36
.37から液体金属温度制御装置38に入力される温度
信号S1、S2の両者の差が予め定められた一定値以内
となり、液体金属温度制御装置38により冷却配管35
に配設される開■j弁34が開とされ、冷却配管35へ
の冷却媒体の流通は停止させられる。Note that when the temperatures of the liquid metal flowing in the upper and lower parts of the horizontal pipe 25 are approximately equal, the temperature measuring means 36
.. 37 to the liquid metal temperature control device 38 becomes within a predetermined constant value, and the liquid metal temperature control device 38 controls the cooling piping 35.
The open valve 34 disposed in the cooling pipe 35 is opened, and the flow of the cooling medium to the cooling pipe 35 is stopped.
「発明の効果」
以上述べたように本発明の高速増殖炉の水平配管温度分
布緩和装置によれば、例えば、原子炉のトリップ時にお
ける層化現象によるホットレグ配管の周方向温度不均一
分布を本発明の実施された配管以降にa)いては完全に
解消することができ、ホットレグ配管の健全性の向上さ
れたより安全な液体金属冷却形高速増殖炉を提供するこ
とができる。``Effects of the Invention'' As described above, according to the horizontal pipe temperature distribution relaxation device for a fast breeder reactor of the present invention, for example, the non-uniform circumferential temperature distribution of hot leg piping due to the stratification phenomenon during a reactor trip can be alleviated. Since the piping in which the invention is implemented, the problem a) can be completely eliminated, and a safer liquid metal cooled fast breeder reactor with improved hot leg piping integrity can be provided.
第1図は従来の液体金属冷却形高速増殖炉を示づ縦断面
図、第2図は高速増殖炉の液体金属系を示す配管系統図
、第3図は本発明の高速増殖炉の水平配管温度分布緩和
装置の一実施例を示を縦断面図、第4図は第3図のTV
−IV線に沿う横断面図である。
1・・・・・・・・・・・・原子炉容器25・・・・・
・・・・・・・水平配管33−・・・・・・・・・・・
保温材
35・・・・・・・・・・・・冷却配管36.37・・
・温度計測手段
38・・・・・・・・・・・・液体金属温度制御装置代
理人弁理士 須 山 佐 −
第1図
第2図
第3図Figure 1 is a vertical cross-sectional view showing a conventional liquid metal cooled fast breeder reactor, Figure 2 is a piping system diagram showing the liquid metal system of the fast breeder reactor, and Figure 3 is the horizontal piping of the fast breeder reactor of the present invention. A longitudinal sectional view showing an embodiment of the temperature distribution relaxation device, FIG. 4 is a TV shown in FIG. 3.
- It is a cross-sectional view along the IV line. 1......Reactor vessel 25...
・・・・・・Horizontal piping 33-・・・・・・・・・・・・
Heat insulation material 35...... Cooling piping 36.37...
・Temperature measurement means 38・・・・・・・・・Liquid metal temperature control device Patent attorney Satoshi Suyama - Figure 1 Figure 2 Figure 3
Claims (1)
属系の水平配管の上部を冷却する冷却手段と、前記水平
配管の上部および下部の温度をそれぞれ測定する温度計
測手段と、これらの温度計測手段から前記水平配管の上
部および下部の温度をそれぞれ示す温度信号を入力し両
者の差が予め定められた一定110を越えた時に前記冷
却手段を作動する液゛体金属温度制御装置とからなるこ
とを特徴とする高速増殖炉の水平配管温度分布緩和装置
。(1) A cooling means for cooling the upper part of the horizontal piping of the primary liquid metal system that circulates liquid metal in the reactor vessel, a temperature measuring means for measuring the temperature of the upper and lower parts of the horizontal piping, and a liquid metal temperature control device that inputs temperature signals indicating the temperatures at the upper and lower portions of the horizontal pipe from the temperature measuring means, and operates the cooling means when the difference between the two exceeds a predetermined constant value of 110; A horizontal piping temperature distribution relaxation device for a fast breeder reactor, which is characterized by:
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP58000987A JPS59126294A (en) | 1983-01-07 | 1983-01-07 | Relaxation device for horizontal pipe temperature distribution of fast breeder |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP58000987A JPS59126294A (en) | 1983-01-07 | 1983-01-07 | Relaxation device for horizontal pipe temperature distribution of fast breeder |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS59126294A true JPS59126294A (en) | 1984-07-20 |
Family
ID=11488948
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP58000987A Pending JPS59126294A (en) | 1983-01-07 | 1983-01-07 | Relaxation device for horizontal pipe temperature distribution of fast breeder |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS59126294A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
USRE37041E1 (en) | 1990-06-08 | 2001-02-06 | Yamaha Corporation | Voice processor |
-
1983
- 1983-01-07 JP JP58000987A patent/JPS59126294A/en active Pending
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
USRE37041E1 (en) | 1990-06-08 | 2001-02-06 | Yamaha Corporation | Voice processor |
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Takahashi | Fundamental Study on Critical Heat Flux in Tight Lattice Core for High Conversion Boiling Water Reactor |