JPH0738037B2 - Temperature control type material irradiation device - Google Patents
Temperature control type material irradiation deviceInfo
- Publication number
- JPH0738037B2 JPH0738037B2 JP4210339A JP21033992A JPH0738037B2 JP H0738037 B2 JPH0738037 B2 JP H0738037B2 JP 4210339 A JP4210339 A JP 4210339A JP 21033992 A JP21033992 A JP 21033992A JP H0738037 B2 JPH0738037 B2 JP H0738037B2
- Authority
- JP
- Japan
- Prior art keywords
- tube
- temperature
- gas
- temperature control
- sodium
- 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 - Fee Related
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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Sampling And Sample Adjustment (AREA)
- Investigating Or Analyzing Materials Using Thermal Means (AREA)
Description
【0001】[0001]
【産業上の利用分野】本発明は、炉心材料について放射
線照射の影響を試験するために用いる材料照射装置に関
する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a material irradiation apparatus used for testing the effects of irradiation on core materials.
【0002】[0002]
【従来の技術】この温度制御型材料照射装置は、被覆管
などの炉心材料の試料に一定温度下で放射線を照射し、
放射線照射による試料の特性変化を測定するために用い
るものであり、液体ナトリウムで満たされた原子炉炉心
に、燃料集合体の間に配置して用いる。This temperature control type material irradiation device irradiates a sample of core material such as a cladding tube with radiation at a constant temperature,
It is used to measure the characteristic change of the sample due to radiation irradiation, and is arranged between the fuel assemblies in the reactor core filled with liquid sodium.
【0003】ところで照射試料に放射線が照射されると
発熱して照射試料の温度が上昇するが、試験上からは照
射試料の温度を所定値に保持した状態で照射を行なうこ
とが要求されている。このような要求を満たすため、上
記従来技術では、動力炉・核燃料開発事業団のパンフレ
ット PNC TN2530 90-001に記載されている様に、内筒
管と外筒管からなる装置が用いられている。照射試料は
内筒管内に保持されてナトリウムに浸漬されている。ナ
トリウムは、炉心から内筒管端面に設けられたナトリウ
ム流入管より内筒管に流入して照射試料と内筒管に放射
線の一種のガンマ線を照射する。そこで発生する熱はナ
トリウムにより内筒管へ伝へられる。内筒管と外筒管の
間にガスギャップを設け、ガスギャップには外筒管端面
に設けられた冷却温度制御用ガス流入・流出管によりガ
スを充填・置換して冷却を行っている。冷却温度制御用
ガスは、熱伝導度の良好なヘリウムガスと熱伝導度の悪
いアルゴンガスを混合してその時の炉心出力に見合った
混合比に設定して内筒管から外筒管への熱伝達を制御し
て照射試料の温度を一定に保つ。When the irradiated sample is irradiated with radiation, the temperature of the irradiated sample rises and the temperature of the irradiated sample rises, but it is required from the test that irradiation is performed while the temperature of the irradiated sample is kept at a predetermined value. . In order to meet such requirements, the above-mentioned conventional technology uses a device composed of an inner tube and an outer tube as described in the pamphlet PNC TN2530 90-001 of the Power Reactor and Nuclear Fuel Development Corporation. . The irradiated sample is held in the inner tube and immersed in sodium. Sodium flows into the inner tube from the core through a sodium inflow tube provided on the end surface of the inner tube, and irradiates the irradiation sample and the inner tube with a kind of gamma ray of radiation. The heat generated there is transferred to the inner tube by sodium. A gas gap is provided between the inner cylindrical pipe and the outer cylindrical pipe, and the gas is cooled by filling and replacing the gas with the cooling temperature control gas inflow / outflow pipes provided at the end surface of the outer cylindrical pipe. The cooling temperature control gas is a mixture of helium gas with good thermal conductivity and argon gas with poor thermal conductivity, set to a mixing ratio that matches the core output at that time, and the heat from the inner tube to the outer tube is set. Control the transfer to keep the temperature of the irradiated sample constant.
【0004】常時内筒管温度をモニターしておいて、炉
心出力変動等により生ずる温度変化に応じ、温度制御系
により上述した混合ガスの混合比を設定し、別途設置し
てあるガス混合タンクに混合ガスを製作充填して、ガス
流入管からガスギャップへガスを送りこみ、既存のガス
はガス流出管から流出させて置換する。The inner tube temperature is constantly monitored, and the above-mentioned mixing ratio of the mixed gas is set by the temperature control system according to the temperature change caused by the fluctuation of the core output, etc., and the gas mixing tank is installed separately. The mixed gas is manufactured and filled, the gas is sent from the gas inflow pipe to the gas gap, and the existing gas is flowed out from the gas outflow pipe to be replaced.
【0005】[0005]
【発明が解決しようとする課題】上述した従来技術で
は、モニターしている内筒内温度の変化を検出してから
ガスギャップのガスを置換するのに、混合ガス製作とガ
ス置換に10分程度は要することから、長時間にわたる
炉心出力変動等による内筒管内温度変化に対しては、ど
うしても温度制御に時間遅れが生じる。In the above-mentioned prior art, in order to replace the gas in the gas gap after detecting the change in the temperature in the inner cylinder being monitored, it takes about 10 minutes to prepare the mixed gas and replace the gas. Therefore, the temperature control inevitably has a time delay with respect to the temperature change in the inner cylinder pipe due to the core output fluctuation and the like over a long period of time.
【0006】また、混合ガスを置換して温度を制御する
ので、制御される温度が階段状になり、従って試料の温
度が階段状となったり、制御系でかなり精度良く混合ガ
スを設定したり制御したりしないと内筒管内温度が、目
標温度を中心に上下に振れて振動が発生してしまうこと
から、連続的に速やかに目標温度が得られる温度制御が
必要となる。Further, since the temperature is controlled by substituting the mixed gas, the temperature to be controlled has a stepwise shape, so that the temperature of the sample has a stepwise shape, and the mixed gas is set with high accuracy by the control system. If the temperature is not controlled, the temperature inside the inner tube fluctuates up and down around the target temperature and vibration occurs. Therefore, it is necessary to control the temperature so that the target temperature can be continuously and quickly obtained.
【0007】特に、照射試料の照射温度は照射材料の試
験結果に大きい影響を及ぼすので試験上非常に重要な因
子である。そのため照射材料提供側からは極力変化の少
ない照射温度が要求されており、階段状の温度変化は好
ましくない。Particularly, the irradiation temperature of the irradiated sample has a great influence on the test result of the irradiated material and is a very important factor in the test. Therefore, the irradiation material providing side requires an irradiation temperature with a minimum change, and a stepwise temperature change is not preferable.
【0008】本発明の目的は、炉心出力変動等によって
生じる照射試料の温度変化を、冷却温度制御用ガスを置
換することなく防止して、照射試料の温度を一定に保持
できる温度制御型材料照射装置を提供することである。It is an object of the present invention to prevent the temperature change of an irradiated sample caused by fluctuations in core power, etc. without replacing the cooling temperature control gas, and to keep the temperature of the irradiated sample constant. It is to provide a device.
【0009】[0009]
【課題を解決するための手段】上記目的を達成するため
に、両端が閉塞され照射試料が収納される内筒管と、両
端が閉塞され前記内筒管が同心状に収納される外筒管
と、前記内筒管の一方の端面に連結されたナトリウム流
入管及び他の端面に連結されたナトリウム流出管と、前
記外筒管に連結されたガスの供給管及び流出管を備えて
なる温度制御型材料照射装置において、前記内筒管を前
記外筒管より熱膨張率の大きい材質により形成したこと
を特徴とする温度制御型材料照射装置としたのである。In order to achieve the above object, an inner cylindrical tube having both ends closed to accommodate an irradiation sample and an outer cylindrical tube having both ends closed to accommodate the inner cylindrical tube concentrically A temperature provided with a sodium inflow pipe connected to one end surface of the inner cylindrical pipe and a sodium outflow pipe connected to the other end surface, and a gas supply pipe and an outflow pipe connected to the outer cylindrical pipe. In the control type material irradiation device, the temperature control type material irradiation device is characterized in that the inner cylindrical tube is formed of a material having a larger thermal expansion coefficient than the outer cylindrical tube.
【0010】[0010]
【作用】このように構成することにより、本発明によれ
ば次の作用により上記の目的が達成される。温度制御型
材料照射装置においては、外筒管の温度は炉心を流れる
ナトリウムにより常時冷却されているので変化は少な
い。しかし内筒管内部の部材温度は、外筒管と内筒管間
のガスギャップを介して外筒管外部より冷却されること
から、ガスギャップの熱伝達率により、また炉心出力変
動に比例して変動する。With this structure, the above-mentioned object can be achieved by the present invention by the following operations. In the temperature control type material irradiation device, the temperature of the outer tube hardly changes because it is constantly cooled by sodium flowing through the core. However, the member temperature inside the inner tube is cooled from the outside of the outer tube through the gas gap between the outer tube and the inner tube, so it depends on the heat transfer coefficient of the gas gap and is proportional to the core power fluctuation. Fluctuate.
【0011】照射試料を保持する内筒管の材質の熱膨張
率が、外筒管より大きいものを採用すると、原子炉炉心
の出力が上昇する時には、内筒管へ流入するナトリウム
のガンマ線による発熱が増加して内筒管温度が上昇、そ
れに伴いガスギャップが縮小して冷却効果が向上する。
逆に出力が低下して内筒管温度が低下する時には、ガス
ギャップが拡大して冷却効果が低下する。このように内
筒管の冷却が制御され、そして、それが炉心出力変動に
よる照射試料の温度変動を打ち消すように作用するので
目的が達成される。If a material having a coefficient of thermal expansion larger than that of the outer tube is used for the material of the inner tube for holding the irradiated sample, when the output of the reactor core is increased, the heat generated by gamma rays of sodium flowing into the inner tube is generated. Increases, the temperature of the inner tube rises, and the gas gap shrinks accordingly, improving the cooling effect.
Conversely, when the output decreases and the inner tube temperature decreases, the gas gap widens and the cooling effect decreases. In this way, the cooling of the inner tube is controlled, and since it acts so as to cancel the temperature fluctuation of the irradiated sample due to the core power fluctuation, the purpose is achieved.
【0012】[0012]
【実施例】以下、本発明の一実施例を図1により説明す
る。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the present invention will be described below with reference to FIG.
【0013】温度制御型材料照射装置の構造は、図1に
示すように照射試料7を保持する内筒管6と内筒管端栓
8とナトリウム流入管3とナトリウム流出管9よりなる
内筒管部と、冷却温度制御用ガス2を保持する外筒管4
とガス流入管1とガス流出管10と外筒管端栓11より
なる外筒部より構成される。As shown in FIG. 1, the structure of the temperature control type material irradiation device has an inner cylinder composed of an inner cylinder tube 6 holding an irradiation sample 7, an inner cylinder tube end plug 8, a sodium inflow tube 3 and a sodium outflow tube 9. Tube part and outer cylinder tube 4 for holding the cooling temperature control gas 2
And a gas inflow pipe 1, a gas outflow pipe 10, and an outer cylinder pipe end plug 11, which is an outer cylinder portion.
【0014】ガスギャップ5による冷却コントロールの
作用を説明する。照射試料7は内筒管内ナトリウム12
に浸漬されており、内筒管6と内筒管端栓8により保持
される。ナトリウム12は、ナトリウム流入管3より内
筒内に流入して照射試料7と内筒管6のガンマ線による
発熱を内筒管6に伝熱する。The operation of cooling control by the gas gap 5 will be described. Irradiated sample 7 is sodium 12 in the inner tube.
And is held by the inner tube 6 and the inner tube end plug 8. The sodium 12 flows into the inner cylinder through the sodium inflow pipe 3 and transfers the heat generated by the gamma rays of the irradiation sample 7 and the inner cylinder 6 to the inner cylinder 6.
【0015】炉心が発生する放射線は、原子炉炉心の出
力変動幅に比例して変動することから、温度制御型材料
照射装置の部材に発生するガンマ線によるガンマ発熱量
は炉心出力変動量に比例して変動する。材料照射装置の
外筒管4は炉心を流れるナトリウムにより常時冷却され
ているので温度変化は殆どないとみてよい程度に少な
い。しかし内筒管6内部の部材は、ガスギャップ5を介
して外部より冷却されることから、その温度はガスギャ
ップ5の熱伝達率と炉心出力変動に応じて変動する。Since the radiation generated by the core fluctuates in proportion to the fluctuation range of the power output of the reactor core, the amount of gamma heat generated by gamma rays generated in the members of the temperature control type material irradiation apparatus is proportional to the fluctuation amount of the core output. Fluctuate. Since the outer tube 4 of the material irradiation apparatus is constantly cooled by sodium flowing through the core, the temperature change is small enough to be considered to be almost unchanged. However, since the member inside the inner tube 6 is cooled from the outside through the gas gap 5, its temperature fluctuates according to the heat transfer coefficient of the gas gap 5 and the fluctuation of the core output.
【0016】そこで、内筒管6に熱膨張率の大きな材質
を採用した場合、炉心出力低下により内筒内のガンマ発
熱が減少すると内筒管6の温度が下がり、熱膨張率に比
例して直径が収縮する。外筒管4は温度低下が少ないこ
とと熱膨張率の小さい材質を用いているので内筒管6よ
り収縮が少ない。このことにより、出力低下時にはガス
ギャップ5幅が拡大する。その結果、内筒管6から外筒
管4への熱伝達が悪くなり、冷却効果が低下することか
ら内筒管6を含む内筒内の温度が上昇する。Therefore, when a material having a large coefficient of thermal expansion is used for the inner tube 6, the temperature of the inner tube 6 decreases when the gamma heat in the inner tube decreases due to a decrease in core output, and the temperature of the inner tube 6 is proportional to the coefficient of thermal expansion. The diameter shrinks. Since the outer tube 4 is made of a material having a small temperature drop and a small coefficient of thermal expansion, it contracts less than the inner tube 6. As a result, the width of the gas gap 5 increases when the output decreases. As a result, the heat transfer from the inner cylinder tube 6 to the outer cylinder tube 4 deteriorates, and the cooling effect decreases, so that the temperature in the inner cylinder including the inner cylinder tube 6 rises.
【0017】逆に炉心出力が上昇した場合、炉心の放射
線が増大して内筒管6内部の部材のガンマ線による発熱
が、そして温度が上昇する。この温度上昇により内筒管
6直径が熱膨張により増大する。外筒管4は温度上昇が
低いことと熱膨張率の小さい材質を採用しているので内
筒管6の直径より、増大の程度が少ない。このことによ
り出力上昇時にはガスギャップ5幅が縮小する。その結
果、内筒管6から外筒管4側への熱伝達が良くなり、冷
却効果が増大することから内筒管6を含む内筒内の温度
が低下する。On the contrary, when the core output is increased, the radiation of the core is increased, the heat generated by the gamma rays of the members inside the inner tube 6 is increased, and the temperature is increased. Due to this temperature rise, the diameter of the inner cylindrical tube 6 increases due to thermal expansion. Since the outer tube 4 has a low temperature rise and is made of a material having a small coefficient of thermal expansion, the degree of increase is smaller than the diameter of the inner tube 6. This reduces the width of the gas gap 5 when the output increases. As a result, the heat transfer from the inner cylinder pipe 6 to the outer cylinder pipe 4 side is improved, and the cooling effect is increased, so that the temperature in the inner cylinder including the inner cylinder pipe 6 is lowered.
【0018】本実施例を原子炉炉心に設置した場合、原
子炉炉心の出力変動5%が運転サイクルに行われるが、
この変動に比例する放射線量の変動により内筒部の部
材、つまり内筒管6、内筒管端栓8、照射試料7等のガ
ンマ線発熱量が変動して温度が変動する。この温度変動
により外筒管4より熱膨張率の大きい材質を採用するこ
とによりガスギャップ5幅をコントロールする。例えば
内筒管6をオーステナイト系ステンレス鋼、外筒管4を
フェライト系ステンレス鋼を採用することにより両者の
熱膨張率に30%程度の差を設定できる。When this embodiment is installed in the reactor core, the output fluctuation of the reactor core is 5%, and
Due to the variation of the radiation dose proportional to this variation, the gamma ray calorific value of the members of the inner cylinder part, that is, the inner cylinder tube 6, the inner cylinder tube end plug 8, the irradiated sample 7, etc., fluctuates and the temperature also fluctuates. The width of the gas gap 5 is controlled by using a material having a coefficient of thermal expansion larger than that of the outer tube 4 due to this temperature fluctuation. For example, by adopting austenitic stainless steel for the inner tubular tube 6 and ferritic stainless steel for the outer tubular tube 4, it is possible to set a difference of about 30% in the coefficient of thermal expansion between the two.
【0019】通常の運転状態では、外筒管4の接するナ
トリウム温度は約450度であり、照射試料7の温度は
650乃至700度程度である。炉心の5%の出力上昇
に対して照射試料7の温度上昇は10度程度となる。そ
れに対し本実施例のガスギャップ5が1mmである場
合、ガスギャップ5の縮小は2%程度であり、これによ
る熱伝達率の向上は約2%となり、その結果、照射試料
7の温度低下は約8度となる。このように、照射試料7
等の温度上昇は抑制され照射試料7の温度は殆ど一定に
保たれる。In a normal operating condition, the temperature of the sodium in contact with the outer tube 4 is about 450 degrees, and the temperature of the irradiated sample 7 is about 650 to 700 degrees. The temperature rise of the irradiated sample 7 is about 10 degrees with respect to the 5% power rise of the core. On the other hand, when the gas gap 5 of the present embodiment is 1 mm, the reduction of the gas gap 5 is about 2%, and the heat transfer coefficient is improved by about 2%. As a result, the temperature of the irradiated sample 7 is not lowered. It will be about 8 degrees. In this way, the irradiation sample 7
The temperature rise of the irradiation sample 7 is suppressed and the temperature of the irradiated sample 7 is kept almost constant.
【0020】また、ガスギャップ5を0.5mmとする
と、上述した場合よりも、効果が大きく、照射試料7の
温度上昇は約1度に抑えられる。When the gas gap 5 is 0.5 mm, the effect is greater than in the above case, and the temperature rise of the irradiated sample 7 can be suppressed to about 1 degree.
【0021】一方炉心出力下降時にはガスギャップ5が
拡大する。拡大量は出力上昇時の縮小量と同様であり、
従って照射試料7の温度低下も上述した程度に抑えられ
る。On the other hand, the gas gap 5 expands when the core power decreases. The amount of expansion is the same as the amount of contraction when the output increases,
Therefore, the temperature drop of the irradiated sample 7 can be suppressed to the above-mentioned level.
【0022】上述した温度制御は、炉心出力上昇・下降
に対して、殆ど同時にガスギャップ5幅が縮小・拡大す
ることからこの温度制御は連続的で非常にスムーズなも
のとなる。この場合、内筒管6材質をオーステナイト系
ステンレス鋼、外筒管4材質をフェライト系ステンレス
鋼を採用したケースを考えたが、もっと熱膨張率の差の
大きな材質を採用すれば温度制御の効果は顕著なものと
なる。The temperature control described above is continuous and extremely smooth because the width of the gas gap 5 is contracted / expanded almost at the same time as the core output is increased / decreased. In this case, we considered the case where austenitic stainless steel was used as the material of the inner tube 6 and ferritic stainless steel was used as the material of the outer tube 4, but if a material with a larger difference in thermal expansion coefficient is used, the temperature control effect will be improved. Becomes noticeable.
【0023】また、ガス混合タンクを含む温度制御系
は、混合ガスを製作する設備が不可欠であることから設
備全体が大がかりなものとなり、原子炉内部での設置場
所の確保が困難となっている。設備が大がかりで複雑な
分、故障の可能性も大きくなるが、本設備は炉心内部に
設置する機器であることから、任意の時に補修すること
は不可能である。本実施例によればこれらの大がかりな
設備は不要となる。Further, since the temperature control system including the gas mixing tank is indispensable for the equipment for producing the mixed gas, the entire equipment becomes large-scale, and it is difficult to secure the installation place inside the reactor. . Although the equipment is large and complicated, the possibility of failure increases, but since this equipment is installed inside the core, it is impossible to repair it at any time. According to this embodiment, these large-scale facilities are unnecessary.
【0024】[0024]
【発明の効果】本発明によれば、内筒管を外筒管より熱
膨張率の大きい材質により形成したので、内筒管の温度
に応じて内筒管と外筒管のガスギャップが変化し、それ
らの間の熱伝達率が変化する。これによって内筒管の冷
却効果が、内筒管温度変化を打ち消すように変化するか
ら、照射試料の温度をほぼ一定に保持する効果がある。According to the present invention, since the inner tube is made of a material having a coefficient of thermal expansion larger than that of the outer tube, the gas gap between the inner tube and the outer tube changes according to the temperature of the inner tube. However, the heat transfer coefficient between them changes. As a result, the cooling effect of the inner cylindrical tube changes so as to cancel the temperature change of the inner cylindrical tube, so that there is an effect of keeping the temperature of the irradiated sample substantially constant.
【0025】また、大がかりな混合ガス製造設備が不要
となるので、製造設備を設置する場所も節約できる効果
がある。Further, since a large-scale mixed gas production facility is not required, there is an effect that the place where the production facility is installed can be saved.
【図1】本発明の一実施例を示す断面図である。FIG. 1 is a sectional view showing an embodiment of the present invention.
1 ガス流入管 2 冷却温度制御用ガス 3 ナトリウム流入管 4 外筒管 5 ガスギャップ 6 内筒管 7 照射試料 8 内筒管端栓 9 ナトリウム流出管 10 ガス流出管 11 外筒管端栓 12 ナトリウム 1 Gas Inflow Pipe 2 Cooling Temperature Control Gas 3 Sodium Inflow Pipe 4 Outer Tube 5 Gas Gap 6 Inner Tube 7 Irradiated Sample 8 Inner Tube End Plug 9 Sodium Outflow Tube 10 Gas Outflow Tube 11 Outer Tube End Plug 12 Sodium
Claims (1)
筒管と、両端が閉塞され前記内筒管が同心状に収納され
る外筒管と、前記内筒管の一方の端面に連結されたナト
リウム流入管及び他の端面に連結されたナトリウム流出
管と、前記外筒管に連結されたガスの供給管及び流出管
とを備えてなる温度制御型材料照射装置において、前記
内筒管を前記外筒管より熱膨張率の大きい材質により形
成したことを特徴とする温度制御型材料照射装置。1. An inner cylindrical tube having both ends closed to accommodate an irradiation sample, an outer cylindrical tube having both ends closed to accommodate the inner cylindrical tube concentrically, and an inner cylindrical tube connected to one end surface of the inner cylindrical tube. In the temperature control type material irradiation device, the inner tube is provided with a sodium inflow tube and a sodium outflow tube connected to the other end surface, and a gas supply tube and an outflow tube connected to the outer tube. The temperature control type material irradiation device is characterized in that the outer tube is made of a material having a coefficient of thermal expansion larger than that of the outer tube.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4210339A JPH0738037B2 (en) | 1992-08-06 | 1992-08-06 | Temperature control type material irradiation device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4210339A JPH0738037B2 (en) | 1992-08-06 | 1992-08-06 | Temperature control type material irradiation device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH0659091A JPH0659091A (en) | 1994-03-04 |
| JPH0738037B2 true JPH0738037B2 (en) | 1995-04-26 |
Family
ID=16587776
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP4210339A Expired - Fee Related JPH0738037B2 (en) | 1992-08-06 | 1992-08-06 | Temperature control type material irradiation device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0738037B2 (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP3507036B2 (en) | 2001-01-18 | 2004-03-15 | 株式会社呉竹 | Writing implement |
| CN111678942B (en) * | 2020-05-08 | 2023-09-19 | 江苏禹治流域管理技术研究院有限公司 | Device and method for testing wet expansion coefficient of fiber composite material |
-
1992
- 1992-08-06 JP JP4210339A patent/JPH0738037B2/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0659091A (en) | 1994-03-04 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US4318776A (en) | Measuring lance for boiling-water nuclear reactors | |
| Saadati et al. | Safety margin and fuel cycle period enhancements of VVER-1000 nuclear reactor using water/silver nanofluid | |
| CN102867554A (en) | Modular bushing type irradiation in-pile verification device | |
| CN1153573A (en) | Method and system for accurately calculating PWR power from excore detector current | |
| Cheng et al. | Critical heat flux and turbulent mixing in hexagonal tight rod bundles | |
| JPH0738037B2 (en) | Temperature control type material irradiation device | |
| CN112863709A (en) | Fast reactor fuel element irradiation test device and method suitable for high heat release power | |
| Hori et al. | Void fraction in a single channel simulating one subchannel of a PWR fuel assembly | |
| Elias et al. | Development and validation of a transition boiling model for RELAP5/MOD3 reflood simulation | |
| Negi et al. | Full length channel Pressure Tube sagging under completely voided full length pressure tube of an Indian PHWR | |
| Markley et al. | LMFBR blanket assembly heat transfer and hydraulic test data evaluation | |
| Poole et al. | Simulator test to study hot-flow problems related to a gas cooled reactor | |
| KR850002359A (en) | Nondestructive Measurement Method and Apparatus for Nuclear Fuel Combustion | |
| Savage et al. | OPERATION OF MOLTEN-SALT CONVECTION LOOPS IN THE ORR. | |
| Gui et al. | Experimental Investigation on Critical Heat Flux in Bilaterally Heated Annulus with equal heat flux on both sides | |
| Ajay et al. | Understanding the influence of eccentric pressure tube on the thermal behavior of 37-element based PHWR channel under accident condition | |
| CN119132662B (en) | Power transient irradiation device suitable for fuel rod bundles | |
| Moons | A calorimetric device for irradiation of FBR fuel pins | |
| Martinson et al. | Reactivity initiated accident test series Test RIA 1-4 | |
| Baroczy et al. | Development of a Variable Orifice for HNPF Fuel Channels | |
| Murphy et al. | The WR-1 corrosion test facility | |
| Felde | Design concept and testing of an in-bundle gamma densitometer for subchannel void fraction measurements in the THTF electrically heated rod bundle.[PWR] | |
| Reynolds | Measurement of Free Fission-Gas Pressure in Operating UO2-Filled Fuel Rods | |
| JPS60183594A (en) | Aggregate for irradiation test of material | |
| Leung | Thermalhydraulics and safety programs in support of the CANDU SCWR design |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| LAPS | Cancellation because of no payment of annual fees |