JPH0334717Y2 - - Google Patents
Info
- Publication number
- JPH0334717Y2 JPH0334717Y2 JP1984089140U JP8914084U JPH0334717Y2 JP H0334717 Y2 JPH0334717 Y2 JP H0334717Y2 JP 1984089140 U JP1984089140 U JP 1984089140U JP 8914084 U JP8914084 U JP 8914084U JP H0334717 Y2 JPH0334717 Y2 JP H0334717Y2
- Authority
- JP
- Japan
- Prior art keywords
- space
- connecting rod
- temperature
- plenum space
- nuclear fuel
- 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
- 239000003758 nuclear fuel Substances 0.000 claims description 23
- 238000001514 detection method Methods 0.000 claims description 17
- 239000000463 material Substances 0.000 claims description 15
- 239000011824 nuclear material Substances 0.000 claims description 5
- 238000005253 cladding Methods 0.000 claims description 4
- 239000007789 gas Substances 0.000 description 18
- 239000008188 pellet Substances 0.000 description 10
- 230000004992 fission Effects 0.000 description 5
- 229910052751 metal Inorganic materials 0.000 description 4
- 239000002184 metal Substances 0.000 description 4
- 229910001220 stainless steel Inorganic materials 0.000 description 3
- 239000010935 stainless steel Substances 0.000 description 3
- 230000005678 Seebeck effect Effects 0.000 description 2
- 230000000712 assembly Effects 0.000 description 2
- 238000000429 assembly Methods 0.000 description 2
- 239000011810 insulating material Substances 0.000 description 2
- 238000005192 partition Methods 0.000 description 2
- 230000002285 radioactive effect Effects 0.000 description 2
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 description 1
- 238000009825 accumulation Methods 0.000 description 1
- 238000009530 blood pressure measurement Methods 0.000 description 1
- 238000009529 body temperature measurement Methods 0.000 description 1
- 230000006835 compression Effects 0.000 description 1
- 238000007906 compression Methods 0.000 description 1
- 229910052802 copper Inorganic materials 0.000 description 1
- 239000010949 copper Substances 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000011261 inert gas Substances 0.000 description 1
- CPLXHLVBOLITMK-UHFFFAOYSA-N magnesium oxide Inorganic materials [Mg]=O CPLXHLVBOLITMK-UHFFFAOYSA-N 0.000 description 1
- 239000000395 magnesium oxide Substances 0.000 description 1
- AXZKOIWUVFPNLO-UHFFFAOYSA-N magnesium;oxygen(2-) Chemical compound [O-2].[Mg+2] AXZKOIWUVFPNLO-UHFFFAOYSA-N 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 150000002739 metals Chemical class 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- BASFCYQUMIYNBI-UHFFFAOYSA-N platinum Chemical compound [Pt] BASFCYQUMIYNBI-UHFFFAOYSA-N 0.000 description 1
- PXXKQOPKNFECSZ-UHFFFAOYSA-N platinum rhodium Chemical compound [Rh].[Pt] PXXKQOPKNFECSZ-UHFFFAOYSA-N 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 238000005245 sintering Methods 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)
Description
【考案の詳細な説明】
〔考案の技術分野〕
本考案は原子炉に用いられる核燃料体に関す
る。[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to a nuclear fuel assembly used in a nuclear reactor.
一般に、原子炉においては核燃料の核分裂によ
つて発生する放射性生成物を幾重にも格納して、
放射性生成物の大気中への漏洩を防止し、安全性
の確保を図つている。
Generally, in a nuclear reactor, radioactive products generated by nuclear fission of nuclear fuel are stored in multiple layers.
Efforts are being made to ensure safety by preventing the leakage of radioactive products into the atmosphere.
核燃料体は核燃料を格納した最も内側の構成要
素であり、通常は酸化物として焼結させた核物質
からなるペレツトを中空長尺な金属性の被覆材内
に充填密封して形成されている。 A nuclear fuel assembly is the innermost component containing nuclear fuel, and is usually formed by filling and sealing pellets of nuclear material sintered as oxides in a hollow, elongated metallic sheath.
この核燃料体において、核分裂生成物は先ずペ
レツト中に閉じ込められるので、ペレツト外のプ
レナム空間内に放出されるのはその一部のみであ
る。そして、プレナム空間内に放出された核分裂
生成物は被覆材によつて漏洩を防止されている。 In this nuclear fuel assembly, the fission products are first confined in the pellet, so only a portion of them is released into the plenum space outside the pellet. The fission products released into the plenum space are prevented from leaking by the covering material.
この被覆材が破損される原因としては種々ある
が、最も多発する可能性のあるものは、プレナム
空間内への核分裂生成物が蓄積して、プレナム空
間内のガス圧力および温度が高くなることであ
る。 This cladding can fail for a variety of reasons, but the most likely cause is the accumulation of fission products in the plenum, increasing the gas pressure and temperature within the plenum. be.
従つて、原子炉の安全性を確保するためには、
核燃料体のプレナム空間内のガス圧力および温度
を常時検知して監視する必要がある。そのため、
従来からプレナム空間内のガス圧力および温度の
検知が行なわれている。 Therefore, in order to ensure the safety of nuclear reactors,
It is necessary to constantly detect and monitor the gas pressure and temperature within the plenum space of the nuclear fuel assembly. Therefore,
Gas pressure and temperature sensing within a plenum space has been conventionally performed.
ところが、従来はプレナム空間内のガス圧力と
温度との測定をそれぞれ別の核燃料体について行
なうものであつたから、検知用ケーブルを複数本
用いなければならず、また炉心への装架位置の異
なる複数の核燃料体について圧力と温度の一方の
みしか検知することができないので安全係数を大
きくして核燃料体の健全性を評価する必要があつ
た。 However, in the past, the gas pressure and temperature in the plenum space were measured for each separate nuclear fuel assembly, which required the use of multiple detection cables, and the measurement of gas pressure and temperature in the plenum space at different locations in the reactor core. Because only one of pressure and temperature can be detected for nuclear fuel assemblies, it was necessary to increase the safety factor to evaluate the integrity of the nuclear fuel assemblies.
本考案はこれらの点に鑑みてなされたものであ
り、同一の核燃料体についてプレナム空間内のガ
ス圧力と温度とを同時に検出することができ、し
かもその検出は１本の検知用ケーブルによつて行
なうことができ、核燃料体の健全性評価の信頼性
を高くすることのできる核燃料体を提供すること
を目的とする。
The present invention was developed in view of these points, and it is possible to simultaneously detect the gas pressure and temperature in the plenum space for the same nuclear fuel assembly, and the detection is performed using a single detection cable. The purpose of the present invention is to provide a nuclear fuel assembly that can be used to evaluate the integrity of a nuclear fuel assembly.
本考案の核燃料体は、被覆材内を核物質が内在
されているプレナム空間と外部からの気体が送給
される外側空間とに仕切るベローズ部材を設け、
先端部が前記外側空間内に挿入されているととも
に前記ベローズ部材と接することにより前記プレ
ナム空間内の圧力と温度とを同時に検知する検知
用ケーブルを設けて形成したことを特徴とする。
The nuclear fuel assembly of the present invention is provided with a bellows member that partitions the inside of the cladding material into a plenum space in which nuclear material is contained and an outer space to which gas from the outside is fed,
The plenum space is characterized by being provided with a detection cable whose tip end is inserted into the outer space and comes into contact with the bellows member to detect the pressure and temperature within the plenum space at the same time.
以下、本考案の実施例を第１図から第３図につ
いて説明する。
Embodiments of the present invention will be described below with reference to FIGS. 1 to 3.
第１図は本考案の核燃料体のプレナム空間部の
ある端部の断面を示している。複数の核燃料体を
炉内の構造物に設置して炉心が構成されている。 FIG. 1 shows a cross section of a certain end of the plenum space of the nuclear fuel assembly of the present invention. A reactor core is constructed by installing a plurality of nuclear fuel bodies in a structure inside the reactor.
図中、符号１は長尺管状の金属製の被覆材であ
り、内部に多数のペレツト２，２を充填密封して
いる。各ペレツト２は核物質を短円柱状に焼結し
て形成されている。これらのペレツト２，２は端
部のペレツト２とストツパ３との間に介装した圧
縮スプリング４によつて被覆材１の一端方向へ弾
圧状態にして定位させられている。また、被覆材
１内の更に端部には、ベローズ部材５が被覆材１
の軸方向に伸縮自在にして設けられている。この
ベローズ部材５はペレツト２，２が内装されてい
るプレナム空間６と、外部から送気管７を介して
不活性ガス等の気体が送給される外側空間８とを
仕切つている。そして、このベローズ部材５は被
覆材１内の縮径部１ａからプレナム空間６側に延
出した内側ベローズ９と、外側空間８側に延出し
た外側ベローズ１０と、両ベローズ９，１０を連
結するステンレス等の金属製の連結杆１１とによ
り形成されている。ストツパ３には通孔３ａが穿
設されている。また、外側空間８内へは、検知用
ケーブル１２の先端が被覆材１の端栓１ｂを貫通
して所定長挿入固定されている。この検知用ケー
ブル１２は、その先端が第１図に示すようにベロ
ーズ部材５の連結杆１１の端面に接触することに
より、プレナム空間６内のガス圧力と温度とを同
時に検知できるように形成されている。第２図は
この検知用ケーブル１２の一実施例であり、酸化
マグネシウム等の絶縁材１３内に、圧力バランス
を検出する圧力接点と温度を検出する温度接点と
を兼ねるために、例えば白金線１４と白金ロジウ
ム線１５とを先端で接合させた異種金属信号線１
６を被覆して形成している。第３図は検知用ケー
ブル１２の他の実施例を示し、絶縁材１３内に１
本の信号線１７を被覆し、この信号線１７を連結
杆１１の材質であるステンレスと異なる材質例え
ば銅によつて形成し、圧力と温度とを同時に検出
できるように形成したものである。 In the figure, reference numeral 1 denotes a long tubular metal covering material, the inside of which is filled and sealed with a large number of pellets 2, 2. Each pellet 2 is formed by sintering nuclear material into a short cylindrical shape. These pellets 2, 2 are elastically positioned toward one end of the covering material 1 by a compression spring 4 interposed between the pellet 2 and the stopper 3 at the end. Furthermore, a bellows member 5 is provided at an end of the covering material 1.
It is provided so that it can be expanded and contracted in the axial direction. This bellows member 5 partitions a plenum space 6 in which the pellets 2, 2 are housed, and an outer space 8 to which gas such as an inert gas is supplied from the outside via an air supply pipe 7. This bellows member 5 connects both bellows 9, 10 with an inner bellows 9 extending from the reduced diameter portion 1a in the covering material 1 toward the plenum space 6 side and an outer bellows 10 extending toward the outer space 8 side. It is formed by a connecting rod 11 made of metal such as stainless steel. The stopper 3 is provided with a through hole 3a. Further, the tip of the detection cable 12 is inserted into the outer space 8 by penetrating the end plug 1b of the covering material 1 and fixed thereto for a predetermined length. This detection cable 12 is formed so that the gas pressure and temperature within the plenum space 6 can be detected simultaneously by having its tip contact the end surface of the connecting rod 11 of the bellows member 5 as shown in FIG. ing. FIG. 2 shows an embodiment of this detection cable 12. For example, a platinum wire 14 is installed in an insulating material 13 such as magnesium oxide to serve as a pressure contact for detecting pressure balance and a temperature contact for detecting temperature. and a platinum-rhodium wire 15 joined at the tip.
It is formed by covering 6. FIG. 3 shows another embodiment of the sensing cable 12, in which one wire is inserted into the insulating material 13.
This signal line 17 is made of a material different from stainless steel, which is the material of the connecting rod 11, such as copper, so that pressure and temperature can be detected simultaneously.
次に、本実施例の作用を説明する。 Next, the operation of this embodiment will be explained.
まず、外側空間８の内圧を大気圧程度にしてお
き、原子炉を運転すると、ペレツト２から核分裂
ガスがプレナム空間６内に放出されて行き、プレ
ナム空間６内の圧力が上昇する。これにより、連
結杆１１には、第１図で右から左方向へ圧力が作
用し、連結杆１１は検知ケーブル１２と圧接した
状態となる。 First, when the reactor is operated with the internal pressure of the outer space 8 at about atmospheric pressure, fission gas is released from the pellets 2 into the plenum space 6, and the pressure within the plenum space 6 increases. As a result, pressure is applied to the connecting rod 11 from the right to the left in FIG. 1, and the connecting rod 11 comes into pressure contact with the detection cable 12.
次に、プレナム空間６の圧力を測定する場合に
は、送気管７を通して気体を外側空間８内に供給
する。外側空間８内の圧力が上昇し、プレナム空
間６より高くなると、連結杆１１には右向きの力
が作用し、連結杆１１が移動して端栓１ｂに固定
されている検知用ケーブル１２の先端から離れ
る。 Next, when measuring the pressure in the plenum space 6, gas is supplied into the outer space 8 through the air pipe 7. When the pressure inside the outer space 8 rises and becomes higher than the plenum space 6, a rightward force acts on the connecting rod 11, causing the connecting rod 11 to move and push the tip of the detection cable 12 fixed to the end plug 1b. move away from
今、ケーブル１２の芯線１５，１６，１７と被
覆材１との間に10ボルトの電圧をかけておくとし
た場合、ケーブル１２と連結杆１１が接触してい
るときは、連結杆１１はベローズ５、被覆材１を
経由して電気的に結合されており、さらにこれら
核燃料体は、原子炉の構造物と連結しているので
接地状態にあり、ケーブル１２の対地電圧はほぼ
０ボルトである。次にケーブル１２が連結杆１１
から分離すると、対地電圧は10ボルトとなる。し
たがつて、送気管７を通して気体を供給し、ケー
ブル１２と連結杆１１との分離、および気体を排
出しての接触を繰返すと、対地電圧は０ボルトと
10ボルトのパルス信号を生ずる。そしてこの０ボ
ルトと10ボルトのときの供給気体圧力を読み取
り、その平均値を算出すれば、プレナム空間６内
の圧力が算出される。すなわち、０ボルト（ケー
ブル１２と連結杆１１とが接触状態となるとき）
の外側空間８への供給気体圧力をＡKg／cm2とし、
10ボルト（ケーブル１２と連結杆１１とが離れた
状態となるとき）の供給気体圧力をＢKg／cm2とす
ると、プレナム空間６の圧力はＡ＋Ｂ／２Kg／cm2と
なる。 Now, if a voltage of 10 volts is applied between the core wires 15, 16, 17 of the cable 12 and the sheathing material 1, when the cable 12 and the connecting rod 11 are in contact, the connecting rod 11 will have a bellows. 5. These nuclear fuel bodies are electrically connected via the sheathing material 1, and are connected to the reactor structure, so they are in a grounded state, and the voltage to the ground of the cable 12 is approximately 0 volts. . Next, the cable 12 connects to the connecting rod 11
When separated from the ground, the voltage to ground is 10 volts. Therefore, if gas is supplied through the air pipe 7, the cable 12 and the connecting rod 11 are separated, and the gas is discharged and the contact is repeated, the voltage to ground becomes 0 volts.
Generates a 10 volt pulse signal. Then, by reading the supplied gas pressure at 0 volts and 10 volts and calculating the average value, the pressure in the plenum space 6 can be calculated. That is, 0 volts (when the cable 12 and the connecting rod 11 are in contact)
The supply gas pressure to the outer space 8 is AKg/cm 2 ,
If the supply gas pressure of 10 volts (when the cable 12 and the connecting rod 11 are separated) is BKg/cm 2 , then the pressure in the plenum space 6 is A+B/2Kg/cm 2 .
同時にプレナム空間６内の温度は次のようにし
て検知される。 At the same time, the temperature within the plenum space 6 is detected as follows.
第２図に示す実施例では、検知用ケーブル１２
内に埋設されている温度検知用ケーブル１４およ
び１５は異種金属であるので、ゼーベツク効果に
より熱起電力が発生し、連結杆１１と接触すれ
ば、連結杆１１の温度をその熱起電力から検知で
きる。連結杆１１の温度はプレナム空間６と同温
度に加温されているので、これによりプレナム空
間６の温度が検知できる。 In the embodiment shown in FIG.
Since the temperature detection cables 14 and 15 buried inside are made of different metals, a thermoelectromotive force is generated due to the Seebeck effect, and when they come into contact with the connecting rod 11, the temperature of the connecting rod 11 is detected from the thermoelectromotive force. can. Since the temperature of the connecting rod 11 is heated to the same temperature as the plenum space 6, the temperature of the plenum space 6 can thereby be detected.
また、第３図に示す実施例のように単芯信号線
１７の場合には、連結杆１１の材質が通常ステン
レスであるので、信号線１７がこれと異種金属で
あれば、両者が接触することにより、同様にゼー
ベツク効果により熱起電力を発生する。そして連
結杆１１は接地状態にあるので、この熱起電力は
信号線１７側に生じ、これを検知することにより
プレナム空間６内の温度を測定することが可能で
ある。 In addition, in the case of a single-core signal line 17 as in the embodiment shown in FIG. 3, the material of the connecting rod 11 is usually stainless steel, so if the signal line 17 is a different metal, the two will come into contact. As a result, a thermoelectromotive force is also generated due to the Seebeck effect. Since the connecting rod 11 is in the grounded state, this thermoelectromotive force is generated on the signal line 17 side, and by detecting this, it is possible to measure the temperature in the plenum space 6.
なお、外側空間８内への送給気体圧力が過大で
あつても、ベローズ部材５の移動はストツパ３に
よつて阻止されるので、安全性を高く維持した状
態で圧力および温度の検出を行なうことができ
る。 Note that even if the pressure of the gas supplied into the outer space 8 is excessive, the movement of the bellows member 5 is prevented by the stopper 3, so pressure and temperature can be detected while maintaining a high degree of safety. be able to.
また、前記した圧力と温度の計測は原子炉の運
転継続的に行なうことができる。 Further, the pressure and temperature measurements described above can be carried out continuously during operation of the nuclear reactor.
このように本考案の核燃料体は、同一の核燃料
体についてプレナム空間内のガス圧力と温度とを
同時に検出することができ、核燃料体の健全性評
価や挙動解明の信頼性を高くすることができ、原
子炉運転の安全性を高くすることができ、しかも
１本の検知用ケーブルによつて温度と圧力を同時
に検出することができるので構造も簡単となり故
障箇所も少なくなる等の効果を奏する。
In this way, the nuclear fuel assembly of the present invention can simultaneously detect the gas pressure and temperature in the plenum space for the same nuclear fuel assembly, increasing the reliability of assessing the health of the nuclear fuel assembly and elucidating its behavior. The safety of nuclear reactor operation can be increased, and since temperature and pressure can be detected simultaneously with one detection cable, the structure is simple and the number of failure points is reduced.
図面は本考案の核燃料体の実施例を示し、第１
図はプレナム空間部を示す核燃料体の端部の縦断
面図、第２図は検知用ケーブルを示す縦断面図、
第３図は検知用ケーブルの他の実施例を示す縦断
面図である。
１……被覆材、２……ペレツト、５……ベロー
ズ部材、、６……プレナム空間、８……外側空間、
９……内側ベローズ、１０……外側ベローズ、１
１……連結杆、１２……検出用ケーブル。
The drawings show an embodiment of the nuclear fuel assembly of the present invention.
The figure is a vertical cross-sectional view of the end of the nuclear fuel assembly showing the plenum space, and Figure 2 is a vertical cross-sectional view showing the detection cable.
FIG. 3 is a longitudinal sectional view showing another embodiment of the detection cable. DESCRIPTION OF SYMBOLS 1... Covering material, 2... Pellet, 5... Bellows member, 6... Plenum space, 8... Outer space,
9...Inner bellows, 10...Outer bellows, 1
1...Connection rod, 12...Detection cable.
Claims (1)
いて、 前記被覆材内を、核物質が内在されているプレ
ナム空間と、外部からの気体が送給される外側空
間とに仕切り、プレナム空間内に延在する内側ベ
ローズと、外側空間内に延在する外側ベローズ
と、これら両ベローズを連結し、原子炉の構造物
と電気的に結合された連結杆とを有するベローズ
部材と； 先端部が前記外側空間内に挿入され、前記連結
杆の端部と接触した際の電流を測定することによ
り前記プレナム空間内の圧力と温度を同時に検知
可能な検知用ケーブルと； からなり、前記検知用ケーブルには、電圧印加手
段が接続され、検知用ケーブルが連結杆の端部に
接触した際、熱起電力を発生させて温度検知可能
に形成されていることを特徴とする核燃料体。[Claims for Utility Model Registration] In a nuclear fuel assembly in which nuclear material is sealed within a cladding material, the cladding material is divided into a plenum space in which the nuclear material is contained and an outside space through which gas is supplied from the outside. an inner bellows extending into the plenum space, an outer bellows extending into the outer space, and a connecting rod that connects both bellows and is electrically connected to the structure of the reactor. a bellows member having; a detection cable whose tip end is inserted into the outer space and is capable of simultaneously detecting the pressure and temperature within the plenum space by measuring the current when it comes into contact with the end of the connecting rod; ; A voltage applying means is connected to the detection cable, and when the detection cable comes into contact with the end of the connecting rod, a thermoelectromotive force is generated so that the temperature can be detected. Nuclear fuel body.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1984089140U JPS6112096U (en) | 1984-06-15 | 1984-06-15 | nuclear fuel body |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1984089140U JPS6112096U (en) | 1984-06-15 | 1984-06-15 | nuclear fuel body |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6112096U JPS6112096U (en) | 1986-01-24 |
| JPH0334717Y2 true JPH0334717Y2 (en) | 1991-07-23 |
Family
ID=30642930
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1984089140U Granted JPS6112096U (en) | 1984-06-15 | 1984-06-15 | nuclear fuel body |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6112096U (en) |
-
1984
- 1984-06-15 JP JP1984089140U patent/JPS6112096U/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6112096U (en) | 1986-01-24 |
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