JPH0360074B2 - - Google Patents
Info
- Publication number
- JPH0360074B2 JPH0360074B2 JP58167978A JP16797883A JPH0360074B2 JP H0360074 B2 JPH0360074 B2 JP H0360074B2 JP 58167978 A JP58167978 A JP 58167978A JP 16797883 A JP16797883 A JP 16797883A JP H0360074 B2 JPH0360074 B2 JP H0360074B2
- Authority
- JP
- Japan
- Prior art keywords
- tritium
- blanket
- production rate
- storage body
- charge storage
- 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 - Lifetime
Links
- YZCKVEUIGOORGS-NJFSPNSNSA-N Tritium Chemical compound [3H] YZCKVEUIGOORGS-NJFSPNSNSA-N 0.000 claims description 43
- 229910052722 tritium Inorganic materials 0.000 claims description 43
- 238000004519 manufacturing process Methods 0.000 claims description 26
- 238000003860 storage Methods 0.000 claims description 26
- 238000000034 method Methods 0.000 claims description 17
- 239000000463 material Substances 0.000 claims description 15
- 230000004927 fusion Effects 0.000 claims description 11
- 239000000470 constituent Substances 0.000 claims description 9
- 229910052744 lithium Inorganic materials 0.000 claims description 9
- 239000000956 alloy Substances 0.000 claims description 8
- 229910045601 alloy Inorganic materials 0.000 claims description 8
- 230000005255 beta decay Effects 0.000 claims description 5
- 238000002347 injection Methods 0.000 claims description 3
- 239000007924 injection Substances 0.000 claims description 3
- 239000010410 layer Substances 0.000 description 14
- 239000004020 conductor Substances 0.000 description 11
- 238000005253 cladding Methods 0.000 description 8
- 239000003963 antioxidant agent Substances 0.000 description 7
- 230000003078 antioxidant effect Effects 0.000 description 7
- 239000011247 coating layer Substances 0.000 description 7
- 238000001514 detection method Methods 0.000 description 7
- WHXSMMKQMYFTQS-UHFFFAOYSA-N Lithium Chemical compound [Li] WHXSMMKQMYFTQS-UHFFFAOYSA-N 0.000 description 4
- 238000006243 chemical reaction Methods 0.000 description 4
- 238000009826 distribution Methods 0.000 description 4
- 230000004907 flux Effects 0.000 description 4
- 238000005259 measurement Methods 0.000 description 4
- 239000011248 coating agent Substances 0.000 description 2
- 238000000576 coating method Methods 0.000 description 2
- 238000007796 conventional method Methods 0.000 description 2
- 239000012777 electrically insulating material Substances 0.000 description 2
- 229910052751 metal Inorganic materials 0.000 description 2
- 239000002184 metal Substances 0.000 description 2
- 239000010935 stainless steel Substances 0.000 description 2
- 229910001220 stainless steel Inorganic materials 0.000 description 2
- 230000005250 beta ray Effects 0.000 description 1
- 230000005540 biological transmission Effects 0.000 description 1
- 229910010293 ceramic material Inorganic materials 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000011156 evaluation Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 229910052734 helium Inorganic materials 0.000 description 1
- 239000001307 helium Substances 0.000 description 1
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 1
- 230000001678 irradiating effect Effects 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000003647 oxidation Effects 0.000 description 1
- 238000007254 oxidation reaction Methods 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 238000005070 sampling Methods 0.000 description 1
- 230000002123 temporal effect Effects 0.000 description 1
- 238000002834 transmittance Methods 0.000 description 1
Classifications
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/16—Measuring radiation intensity
- G01T1/185—Measuring radiation intensity with ionisation chamber arrangements
-
- 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
- Y02E30/10—Nuclear fusion reactors
Landscapes
- Physics & Mathematics (AREA)
- Health & Medical Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Physics & Mathematics (AREA)
- High Energy & Nuclear Physics (AREA)
- Molecular Biology (AREA)
- Spectroscopy & Molecular Physics (AREA)
- Measurement Of Radiation (AREA)
Description
【発明の詳細な説明】
〔発明の技術分野〕
本発明は核融合炉のブランケツト構成材におい
てトリチウムが生成する率を測定する方法に関す
る。DETAILED DESCRIPTION OF THE INVENTION TECHNICAL FIELD OF THE INVENTION The present invention relates to a method for measuring the rate of tritium production in a blanket component of a nuclear fusion reactor.
核融合炉は、一般に、炉心プラズマ、そのまわ
りを囲むブランケツト、およびその外側にあるコ
イルからなつている。ブランケツトはリチウム
（Li）またはその合金と中性子減速材から主に構
成され、高速中性子の熱化および放射線遮蔽など
のほか、次のトリチウム（Ｔ）の増殖の機能を果
す。すなわち、核融合反応でできた高速中性子
は、ブランケツトに入射してエネルギーを与える
とともに、ブランケツト中のリチウムと下記のよ
うに反応して、トリチウムを自己再生産する。
A fusion reactor generally consists of a core plasma, a surrounding blanket, and an outer coil. The blanket is mainly composed of lithium (Li) or its alloy and a neutron moderator, and in addition to thermalizing fast neutrons and shielding radiation, it also functions as a multiplier for tritium (T). That is, fast neutrons produced by the nuclear fusion reaction enter the blanket and provide energy, and react with lithium in the blanket as described below to self-reproduce tritium.
6Li＋ｎ→He＋Ｔ
7Li＋ｎ→He＋Ｔ＋ｎ
この熱エネルギーは外に取り出して発電などに
利用され、また、中性子入射によるトリチウムは
ブランケツト構成材中から回収されて核融合反応
の燃料となる。 6 Li+n→He+T 7 Li+n→He+T+n This thermal energy is taken out and used for power generation, and tritium caused by neutron incidence is recovered from the blanket constituent materials and becomes fuel for the nuclear fusion reaction.
したがつて、核融合炉ブランケツト中への中性
子入射によるトリチウム生成率を知ることが、ト
リチウムをブランケツト構成材から押出・回収す
るか否かの判断にとつて重要である。 Therefore, knowing the tritium production rate due to neutron injection into the fusion reactor blanket is important in determining whether tritium should be extruded and recovered from the blanket constituent materials.
従来、トリチウム生成率を知る方法として、ま
ず、中性子検出器を用いてブランケツトにおける
中性子束を測定し、この測定した中性子束と照射
時間からトリチウム生成率を推定して間接的に測
定する方法がある。 Conventionally, the method of determining the tritium production rate is to first measure the neutron flux in the blanket using a neutron detector, and then estimate the tritium production rate from the measured neutron flux and irradiation time to indirectly measure it. .
しかしながら、この方法ではブランケツトにお
ける中性子束の空間分布、エネルギー分布、時間
分布などの種々の測定を行う必要があり、またリ
チウムの中性子入射によるトリチウム生成反応断
面積を前もつて知つておく必要がある。さらに、
トリチウム生成率を推定するにあたつて非常に煩
雑かつ莫大な計算をしなくてはならず、また、炉
心プラズマを取り巻くブランケツトの個々の要素
におけるトリチウム生成率を知ることが中性子束
の各々の測定の困難さから非常にむずかしい。 However, with this method, it is necessary to perform various measurements such as the spatial distribution, energy distribution, and temporal distribution of neutron flux in the blanket, and it is also necessary to know in advance the tritium production reaction cross section due to neutron incidence of lithium. . moreover,
Estimating the tritium production rate requires very complicated and enormous calculations, and it is difficult to know the tritium production rate in each element of the blanket surrounding the core plasma for each measurement of neutron flux. It is very difficult because of the difficulty of
本発明は上述の事情に鑑みなされたものであ
り、その目的とするところは直接的にかつ容易に
トリチウム生成率を測定することのできる方法を
提供することである。
The present invention has been made in view of the above-mentioned circumstances, and its purpose is to provide a method that can directly and easily measure the tritium production rate.
ブランケツト中で中性子入射により生成したト
リチウムは次式のようにβ崩壊する低エネルギー
β-粒子放出体である。
Tritium generated by neutron injection in the blanket is a low-energy β -particle emitter that undergoes β decay as shown in the following equation.
3T→ 3He +＋ｅ
したがつて、ブランケツト中からβ線が飛び出
した場合ブランケツト構成材にHe +が残留してブ
ランケツト構成材が正に帯電し、しかもトリチウ
ム生成量とその電荷量とが比例する。本発明者は
上記知見にもとずき本発明を完成するに至つた。 3 T→ 3 H e + +e Therefore, when β rays jump out from inside the blanket, H e + remains in the blanket constituent materials and the blanket constituent materials become positively charged, and the amount of tritium produced and its charge are is proportional. The present inventor has completed the present invention based on the above findings.
すなわち、本発明のトリチウム生成率測定方法
は、核融合炉ブランケツトの構成材中での中性子
入射によるトリチウム生成率を測定する方法であ
つて、リチウム金属またはその合金を有する電荷
蓄積体に炉心プラズマからの中性子を照射してト
リチウムを生成させ、生成したトリチウムのβ崩
壊により該蓄積体を帯電させ次いで帯電した蓄積
体の電荷量を検知して該ブランケツトのトリチウ
ム生成率を評価することを特徴とするものであ
る。 That is, the method for measuring the tritium production rate of the present invention is a method for measuring the tritium production rate due to neutron incidence in the constituent materials of a fusion reactor blanket, and is a method for measuring the tritium production rate due to neutron incidence in the constituent materials of a fusion reactor blanket. The blanket is characterized by irradiating it with neutrons to generate tritium, charging the accumulator by β-decay of the generated tritium, and then detecting the amount of charge on the charged accumulator to evaluate the tritium production rate of the blanket. It is something.
本発明のトリチウム生成率の測定法の実施に利
用できる装置の一例を用いて添付図面を参照しつ
つ、本発明の方法を具体的に説明する。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS The method of the present invention will be specifically explained using an example of an apparatus that can be used to carry out the method of measuring the tritium production rate of the present invention with reference to the accompanying drawings.
第１図は電荷蓄積体およびその外郭の断面図で
ある。 FIG. 1 is a cross-sectional view of a charge storage body and its outline.
電荷蓄積体１１は、核融合炉ブランケツトの主
要構成物質であるリチウム金属もしくはその合金
からなる。この合金の組成は好ましくはブランケ
ツトの構成材と同一もしくは類似するものであ
る。電荷蓄積体１１の形状および寸法は炉の種
類、ブランケツトの種類および形状、および測定
位置などにより選択される。好ましくは、球状も
しくは円柱状である。 The charge storage body 11 is made of lithium metal or an alloy thereof, which is the main constituent material of the fusion reactor blanket. The composition of this alloy is preferably the same or similar to the components of the blanket. The shape and dimensions of the charge storage body 11 are selected depending on the type of furnace, the type and shape of the blanket, the measurement location, etc. Preferably, it is spherical or cylindrical.
外郭１２は内層の絶縁層１３と外層の被覆層１
４とからなり、電荷蓄積体１１を覆うように設け
られる。外郭１２は電荷蓄積体１１を保持すると
共に、その絶縁層１３によつて電荷蓄積体１１を
電気的に絶縁する。外郭の形状および寸法は、上
述の電荷蓄積体１１の形状および寸法などにより
決められる。本発明において絶縁層１３は電気的
絶縁性の材料から作られ、好ましくはβ線透過率
の良好な材料から、例えば、Al2O2などのセラミ
ツク材から作られる。また、本発明において被覆
層１４は、その内部の電荷蓄積体１１および絶縁
層１３を保持・保護すべく機械的強度の大きい材
料から作られ、しかも電気伝導性を有する材料か
ら、例えばステンレスなどの金属から作られる。
外郭の一部分において、被覆層１４と絶縁層１３
とを貫通して孔１５が形成される。この孔１５
は、後述する検知装置と前述の電荷蓄積体１１お
よび導電性被覆層１４とを接合すべき箇所であ
る。接触面を広げ、また検知装置と確実に接合す
るように孔１５の被覆層１４の内周面にはネジが
切られている。孔１５の底面の全面にわたつて酸
化防止体１６が設けられる。これは、電荷蓄積体
１１のリチウム金属またはその合金の酸化を防止
し、またそのリチウム金属またはその合金の漏洩
を防止する。酸化防止体１６には、電荷蓄積体１
１と検知装置とを電気的に接続させるように導電
性の材料が使用される。 The outer shell 12 has an inner insulating layer 13 and an outer covering layer 1.
4, and is provided so as to cover the charge storage body 11. The shell 12 holds the charge storage body 11 and electrically insulates the charge storage body 11 by means of its insulating layer 13 . The shape and dimensions of the outer shell are determined by the shape and dimensions of the charge storage body 11 described above. In the present invention, the insulating layer 13 is made of an electrically insulating material, preferably a material with good β-ray transmittance, for example a ceramic material such as Al 2 O 2 . Further, in the present invention, the coating layer 14 is made of a material with high mechanical strength in order to hold and protect the charge storage body 11 and the insulating layer 13 therein, and is made of a material with electrical conductivity, such as stainless steel. made from metal.
In a part of the outer shell, the covering layer 14 and the insulating layer 13
A hole 15 is formed through the. This hole 15
is a location where the detection device described later and the charge storage body 11 and the conductive coating layer 14 described above are to be joined. The inner circumferential surface of the coating layer 14 of the hole 15 is threaded to widen the contact surface and to ensure reliable connection with the detection device. An antioxidant 16 is provided over the entire bottom surface of the hole 15 . This prevents oxidation of the lithium metal or its alloy in the charge storage body 11 and also prevents leakage of the lithium metal or its alloy. The antioxidant 16 includes a charge accumulator 1
An electrically conductive material is used to provide an electrical connection between 1 and the sensing device.
次いで、蓄積体１１での電荷量を検知する検知
装置２０の断面図が第２図である。 Next, FIG. 2 is a cross-sectional view of a detection device 20 that detects the amount of charge in the storage body 11.
信号導線２１はその外周を絶縁管２２で被わ
れ、さらにこの絶縁管はその層の被覆管２３に被
われる。信号導線２１は、電荷蓄積体１１の電荷
量による電気的信号を伝達するように導電性材料
から作られる。絶縁管２２は電気的絶縁性材料か
ら作られ、信号導線２１と導電性の被覆管２３と
を電気的に絶縁させる。被覆管２３は、導電性の
材料から作られ、その内部を保護するように機械
的強度の大きい材料、例えばステンレスなどの金
属から作られる。 The signal conductor 21 is covered on its outer periphery with an insulating tube 22, and this insulating tube is further covered with a cladding tube 23 of that layer. The signal conductor 21 is made of a conductive material so as to transmit an electrical signal depending on the amount of charge on the charge storage body 11 . The insulating tube 22 is made of an electrically insulating material and electrically isolates the signal conductor 21 from the conductive cladding tube 23 . The cladding tube 23 is made of a conductive material, and is made of a material with high mechanical strength, for example, a metal such as stainless steel, so as to protect the inside thereof.
コレクター２４は、検知装置２０の一端に設け
られ、信号導線２１と電気的に接続されるが、絶
縁管２２によつて導電性被覆管２３と電気的に絶
縁され、しかも前述の酸化防止体１６と接触する
ことができるように露出されている。 The collector 24 is provided at one end of the detection device 20 and is electrically connected to the signal conductor 21, but is electrically insulated from the conductive cladding tube 23 by the insulating tube 22, and furthermore, the above-mentioned antioxidant 16 exposed so that it can come into contact with.
コレクター２４がある検知装置の先端部は、前
述の電荷蓄積体１１およびその外郭１２と接続さ
せるために凸状に形成される。この部分における
被覆管２３の端部は、被覆層１４と確実に接合す
るようにその外周面にネジが切られている。 The tip of the sensing device, where the collector 24 is located, is formed in a convex shape in order to connect with the charge storage body 11 and its outer shell 12 described above. The end of the cladding tube 23 in this portion is threaded on its outer circumferential surface so as to be reliably joined to the coating layer 14.
被覆管２３、絶縁管２２および信号導線２１の
寸法は任意に選択されるが、各々の全長は実質的
に等しい。 Although the dimensions of the cladding tube 23, the insulating tube 22, and the signal conductor 21 are arbitrarily selected, the overall lengths of each are substantially equal.
コレクター２４と反対側にある信号導線２１と
被覆管２３との各々の端部に、外部回路２５が電
気的に接続されている。この各々の接続方法は、
伝送されるべき電気的信号の伝達を阻害しない通
常の方法による。 An external circuit 25 is electrically connected to each end of the signal conductor 21 and the cladding tube 23 on the side opposite the collector 24 . The connection method for each of these is
By a normal method that does not interfere with the transmission of electrical signals to be transmitted.
第３図は、前述した第１図と第２図との部材を
組み立てた装置例の断面図である。第３図に示す
ように、外郭１２の孔１５に検知装置の凸状先端
部がはめ合わされる。コレクター２４は酸化防止
体１４を介して電荷蓄積体１１と電気的に接続さ
れ、また被覆管２３は被覆層１４と電気的に接続
される。さらに、電荷蓄積体−酸化防止体−コレ
クターと被覆層−被覆管との間は絶縁管２２およ
び絶縁層１３によつて電気的に絶縁される。 FIG. 3 is a sectional view of an example of an apparatus in which the members shown in FIGS. 1 and 2 described above are assembled. As shown in FIG. 3, the convex tip of the sensing device is fitted into the hole 15 of the outer shell 12. The collector 24 is electrically connected to the charge storage body 11 via the antioxidant 14, and the cladding tube 23 is electrically connected to the coating layer 14. Further, the charge accumulator/antioxidant/collector and the coating layer/coating tube are electrically insulated by the insulating tube 22 and the insulating layer 13.
本発明のトリチウム生成率の測定法の実施に利
用される前述の装置例の使用ならびに作用につい
て説明する。 The use and operation of the above-mentioned example of the apparatus used to carry out the method for measuring the tritium production rate of the present invention will be explained.
第３図に示すように組み立てられた装置の電荷
蓄積体１１の部分が、トリチウム生成率を測定す
べきブランケツトの近傍もしくはその内部に配設
される。他方、検出装置の外部回路２５の部分は
核融合炉外の作業員が安全に操作・測定できる場
所に設置される。上述のように組み立てて配設さ
れた装置の電荷蓄積体１１は、核融合炉の運転時
に炉心プラズマから発生した高速の中性子の照射
を受ける。照射をうけた電荷蓄積体のリチウム金
属またはその合金は、リチウム原子と中性子との
原子核反応によりトリチウムとヘリウムとに変換
してトリチウム生成が起る。このように生成した
トリチウムはβ崩壊により 3He +になり同時に発
生するβ線の一部は、特に電荷蓄積体１１の表面
近くで起こるβ崩壊によるβ線は、絶縁層１３を
透過して被覆層１４に達する。被覆層１４に捕捉
された電子は被覆層１４を負に帯電させ、他方電
荷蓄積体１１には残留する 3He +によつて正の電
荷がたまる。トリチウム生成に起因するこの電荷
蓄積体１１の電荷量はトリチウム生成量に比例す
る。 The charge storage 11 portion of the device assembled as shown in FIG. 3 is placed near or within the blanket whose tritium production rate is to be measured. On the other hand, the external circuit 25 portion of the detection device is installed at a location outside the fusion reactor where it can be safely operated and measured by workers. The charge storage body 11 of the device assembled and arranged as described above is irradiated with high-speed neutrons generated from the core plasma during operation of the fusion reactor. The irradiated lithium metal or its alloy in the charge storage body is converted into tritium and helium through a nuclear reaction between lithium atoms and neutrons, resulting in the production of tritium. The tritium thus generated becomes 3 H e + due to β decay, and some of the β rays generated at the same time, especially the β rays due to β decay that occurs near the surface of the charge storage body 11, are transmitted through the insulating layer 13. The coating layer 14 is reached. The electrons captured in the covering layer 14 charge the covering layer 14 negatively, while the charge storage body 11 accumulates positive charges due to the remaining 3 H e + . The amount of charge in the charge storage body 11 due to tritium generation is proportional to the amount of tritium generated.
次いで、電荷蓄積体１１の電荷量は電導性の酸
化防止体１６を介してコレクター２４に収集さ
れ、この収集された電荷はコレクター２４に電気
的に接続された信号導線２１を通つて外部回路２
５に伝達される。外部回路２５において、伝達さ
れた電荷量に応じて電流が流れ、この電流値が測
定される。 The amount of charge in the charge storage body 11 is then collected in the collector 24 via the conductive antioxidant body 16, and the collected charge is transferred to the external circuit 2 through the signal conductor 21 electrically connected to the collector 24.
5. In the external circuit 25, a current flows according to the amount of transferred charge, and the value of this current is measured.
この測定値より電荷蓄積体１１内のトリチウム
生成率を評価し、こ評価より電荷蓄積体１１が配
置されたブランケツトのトリチウム生成率をさら
に評価することができる。 The tritium production rate within the charge storage body 11 can be evaluated from this measured value, and from this evaluation, the tritium production rate of the blanket in which the charge storage body 11 is placed can be further evaluated.
本発明の方法を使用する装置例は、上述のもの
に限定されるものではなく種々の変形が可能であ
る。 Examples of devices using the method of the present invention are not limited to those described above, and various modifications are possible.
すなわち、炉心プラズマからの中性子の照射に
よりトリチウムが既に生成したブランケツト構成
材の一部を、その流通系からサンプリングして、
それを前述の装置例の外郭１２の中に充填しても
よい。このようにブランケツト構成材の一部をサ
ンプリングすることにより、そのブランケツトの
トリチウム生成率をより直接に評価することが可
能となる。 In other words, a part of the blanket component material in which tritium has already been generated by irradiation with neutrons from the reactor core plasma is sampled from its distribution system.
It may be filled into the shell 12 of the example device described above. By sampling a portion of the blanket constituent material in this manner, it becomes possible to more directly evaluate the tritium production rate of the blanket.
本発明によつて、従来方法よりより直接的にト
リチウム生成率を測定することが可能になり、し
かも測定過程において従来のような煩雑な作業を
必要とせず極めて容易に測定できる。
According to the present invention, it is possible to measure the tritium production rate more directly than in the conventional method, and the measurement process can be performed extremely easily without requiring complicated operations as in the conventional method.
したがつて、本発明の方法によつて容易かつ直
接的にブランケツトの生成率を測定することがで
きるために、トリチウム生成率基準に基づいたト
リチウムを抽出・回収するか否かの判断を、実際
のトリチウム生成量に即して行うことができる。 Therefore, since the blanket production rate can be easily and directly measured by the method of the present invention, it is difficult to actually judge whether or not to extract and recover tritium based on the tritium production rate standard. This can be done depending on the amount of tritium produced.
さらに、本発明の電荷蓄積体を個々のブランケ
ツトにおけるリチウム金属またはその合金とする
ことにより、その個々のブランケツトごとにトリ
チウム生成率を測定できて各々に対してトリチウ
ムを抽出・回収するか否かの判断が可能である。 Furthermore, by using the charge accumulator of the present invention as lithium metal or its alloy in each blanket, the tritium production rate can be measured for each blanket, and it is possible to determine whether or not tritium is extracted and recovered for each blanket. Judgment is possible.
第１図は、電荷蓄積体およびその外郭の断面
図、第２図は検知装置の断面図、および第３図は
第１図および第２図で示した部材を組み立てた装
置の部分断面図である。
１１……電荷蓄積体、１２……外郭、１３……
絶縁層、１４……被覆層、１５……孔、１６……
酸化防止材、２０……検知装置、２１……信号導
線、２２……絶縁管、２３……被覆管、２４……
コレクター、２５……外部回路。
Figure 1 is a sectional view of the charge storage body and its outer shell, Figure 2 is a sectional view of the detection device, and Figure 3 is a partial sectional view of the device assembled with the members shown in Figures 1 and 2. be. 11... Charge storage body, 12... Outer shell, 13...
Insulating layer, 14... Covering layer, 15... Hole, 16...
Antioxidant material, 20...Detection device, 21...Signal conductor, 22...Insulating tube, 23...Coating tube, 24...
Collector, 25...external circuit.
Claims (1)
成材中のトリチウム生成率を測定する方法におい
て、リチウム金属またはその合金からなる電荷蓄
積体に炉心プラズマからの中性子を照射させてト
リチウムを生成させ、生成したトリチウムのβ崩
壊により該蓄積体を帯電させ、次いで帯電した蓄
積体の電荷量を検知して該ブランケツトのトリチ
ウム生成率を評価することを特徴とするトリチウ
ム生成率の測定法。1 In a method of measuring the tritium production rate in the constituent materials of a fusion reactor blanket by neutron injection, a charge storage body made of lithium metal or its alloy is irradiated with neutrons from the core plasma to generate tritium, and the generated tritium A method for measuring the tritium production rate, which comprises charging the accumulator by β decay of the blanket, and then detecting the amount of charge on the charged accumulator to evaluate the tritium production rate of the blanket.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58167978A JPS6058573A (en) | 1983-09-12 | 1983-09-12 | Measurement of tritium forming rate |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58167978A JPS6058573A (en) | 1983-09-12 | 1983-09-12 | Measurement of tritium forming rate |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6058573A JPS6058573A (en) | 1985-04-04 |
| JPH0360074B2 true JPH0360074B2 (en) | 1991-09-12 |
Family
ID=15859539
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58167978A Granted JPS6058573A (en) | 1983-09-12 | 1983-09-12 | Measurement of tritium forming rate |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6058573A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103018315B (en) * | 2012-10-23 | 2015-06-24 | 西北核技术研究所 | A kind of equivalent measurement method and device for the amount of tritium produced by neutron irradiation 6Li |
-
1983
- 1983-09-12 JP JP58167978A patent/JPS6058573A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6058573A (en) | 1985-04-04 |
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