JPS6256474B2 - - Google Patents
Info
- Publication number
- JPS6256474B2 JPS6256474B2 JP56061391A JP6139181A JPS6256474B2 JP S6256474 B2 JPS6256474 B2 JP S6256474B2 JP 56061391 A JP56061391 A JP 56061391A JP 6139181 A JP6139181 A JP 6139181A JP S6256474 B2 JPS6256474 B2 JP S6256474B2
- Authority
- JP
- Japan
- Prior art keywords
- tritium
- carrier
- material according
- breeder
- breeding
- 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
- 229910052722 tritium Inorganic materials 0.000 claims description 62
- YZCKVEUIGOORGS-NJFSPNSNSA-N Tritium Chemical compound [3H] YZCKVEUIGOORGS-NJFSPNSNSA-N 0.000 claims description 61
- 239000000463 material Substances 0.000 claims description 50
- 238000006243 chemical reaction Methods 0.000 claims description 15
- 238000009395 breeding Methods 0.000 claims description 14
- 230000001488 breeding effect Effects 0.000 claims description 14
- 239000000126 substance Substances 0.000 claims description 7
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims description 5
- 229910018068 Li 2 O Inorganic materials 0.000 claims description 5
- 229910010093 LiAlO Inorganic materials 0.000 claims description 5
- 229910002804 graphite Inorganic materials 0.000 claims description 5
- 239000010439 graphite Substances 0.000 claims description 5
- 238000002844 melting Methods 0.000 claims description 5
- 230000008018 melting Effects 0.000 claims description 5
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 claims description 4
- 239000000956 alloy Substances 0.000 claims description 4
- 229910045601 alloy Inorganic materials 0.000 claims description 4
- 150000001875 compounds Chemical class 0.000 claims description 4
- 229910052739 hydrogen Inorganic materials 0.000 claims description 4
- 239000001257 hydrogen Substances 0.000 claims description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 4
- 239000011248 coating agent Substances 0.000 claims description 3
- 238000000576 coating method Methods 0.000 claims description 3
- 229910052750 molybdenum Inorganic materials 0.000 claims description 3
- 229910010199 LiAl Inorganic materials 0.000 claims description 2
- 229910052751 metal Inorganic materials 0.000 claims description 2
- 239000002184 metal Substances 0.000 claims description 2
- 239000012466 permeate Substances 0.000 claims description 2
- 239000006104 solid solution Substances 0.000 claims description 2
- HBBGRARXTFLTSG-UHFFFAOYSA-N Lithium ion Chemical compound [Li+] HBBGRARXTFLTSG-UHFFFAOYSA-N 0.000 claims 1
- ZOKXTWBITQBERF-UHFFFAOYSA-N Molybdenum Chemical compound [Mo] ZOKXTWBITQBERF-UHFFFAOYSA-N 0.000 claims 1
- 229910052790 beryllium Inorganic materials 0.000 claims 1
- ATBAMAFKBVZNFJ-UHFFFAOYSA-N beryllium atom Chemical compound [Be] ATBAMAFKBVZNFJ-UHFFFAOYSA-N 0.000 claims 1
- 239000011733 molybdenum Substances 0.000 claims 1
- LTPBRCUWZOMYOC-UHFFFAOYSA-N beryllium oxide Inorganic materials O=[Be] LTPBRCUWZOMYOC-UHFFFAOYSA-N 0.000 description 7
- 230000004927 fusion Effects 0.000 description 7
- 239000007787 solid Substances 0.000 description 4
- 239000000446 fuel Substances 0.000 description 3
- 229910052744 lithium Inorganic materials 0.000 description 3
- 239000002245 particle Substances 0.000 description 3
- 229910018071 Li 2 O 2 Inorganic materials 0.000 description 2
- WHXSMMKQMYFTQS-UHFFFAOYSA-N Lithium Chemical compound [Li] WHXSMMKQMYFTQS-UHFFFAOYSA-N 0.000 description 2
- 229910052805 deuterium Inorganic materials 0.000 description 2
- 238000009792 diffusion process Methods 0.000 description 2
- 239000007789 gas Substances 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- FRWYFWZENXDZMU-UHFFFAOYSA-N 2-iodoquinoline Chemical compound C1=CC=CC2=NC(I)=CC=C21 FRWYFWZENXDZMU-UHFFFAOYSA-N 0.000 description 1
- YZCKVEUIGOORGS-OUBTZVSYSA-N Deuterium Chemical compound [2H] YZCKVEUIGOORGS-OUBTZVSYSA-N 0.000 description 1
- 238000009825 accumulation Methods 0.000 description 1
- 239000000969 carrier Substances 0.000 description 1
- 230000008094 contradictory effect Effects 0.000 description 1
- 238000000586 desensitisation Methods 0.000 description 1
- 239000000945 filler Substances 0.000 description 1
- 229930195733 hydrocarbon Natural products 0.000 description 1
- 150000002430 hydrocarbons Chemical class 0.000 description 1
- 150000002642 lithium compounds Chemical class 0.000 description 1
- FUJCRWPEOMXPAD-UHFFFAOYSA-N lithium oxide Chemical compound [Li+].[Li+].[O-2] FUJCRWPEOMXPAD-UHFFFAOYSA-N 0.000 description 1
- 229910001947 lithium oxide Inorganic materials 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 150000002739 metals Chemical class 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 238000001228 spectrum Methods 0.000 description 1
- 229910052721 tungsten Inorganic materials 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
- Y02E30/10—Nuclear fusion reactors
Landscapes
- Radiation-Therapy Devices (AREA)
Description
【発明の詳細な説明】
この発明は中性子照射下でトリチウムを生産す
るための固体のトリチウム増殖材に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a solid tritium breeder material for producing tritium under neutron irradiation.
デユーテリウム(D)とトリチウム（Ｔ）を燃料と
するＤ−Ｔ核融合炉では、（Ｄ、Ｔ）反応で発生
する14MeV中性子を熱化し、且つ、天然には殆
んど存在しない燃料トリチウムを再生産するため
のブランケツトがプラズマを取囲んで配置されて
いる。この融合炉ブランケツトは固体のトリチウ
ム増殖材からなるブロツク又はペブルをそのブラ
ンケツト内に充填し、その間隙に高圧のHeガス
を流して熱除去及びトリチウム回収を行なつてい
る。しかるに、この方法ではブランケツトで発生
する熱を除去する為に大流量のHeを流す必要
上、圧損の関係から従来のトリチウム増殖材では
そのトリチウム増殖材ペブルの粒径を少なくとも
30mm程度以上の大きさを必要とし、この程度の大
きさのペブルでは、内部に生成されたトリチウム
又はその化合物がペブル表面まで拡散してくるの
に必要な時間が長くなり、トリチウムの回収効率
が低下する。これは、Ｄ−Ｔ融合炉の燃料サイク
ルにとつて問題であると共に、放射性のトリチウ
ムがブランケツト内に大量に蓄積される事にな
り、諸種の問題の原因となる。 The DT fusion reactor, which uses deuterium (D) and tritium (T) as fuel, thermalizes the 14 MeV neutrons generated in the (D, T) reaction and regenerates the fuel tritium, which hardly exists in nature. A production blanket is placed around the plasma. This fusion reactor blanket is filled with blocks or pebbles made of solid tritium breeder material, and high-pressure He gas is flowed through the gaps to remove heat and recover tritium. However, in this method, it is necessary to flow a large flow of He to remove the heat generated in the blanket, and due to pressure drop, the particle size of the tritium breeder pebble in conventional tritium breeder material is at least
A pebble of this size requires a pebble of approximately 30 mm or more, and the time required for the tritium or its compounds generated inside to diffuse to the pebble surface becomes longer, reducing the tritium recovery efficiency. descend. This is a problem for the fuel cycle of the DT fusion reactor, and a large amount of radioactive tritium accumulates within the blanket, causing various problems.
この発明の目的は、従来の上述した欠点に鑑
み、生成したトリチウムを放出しやすく、従つ
て、又、トリチウム増殖材内へのトリチウム蓄積
の少ない固体のトリチウム増殖材を提供する事に
ある。 SUMMARY OF THE INVENTION In view of the above-mentioned drawbacks of the prior art, it is an object of the present invention to provide a solid tritium breeder material that is easy to release generated tritium and that causes less tritium accumulation in the tritium breeder material.
又、本発明の他の目的は高速中性子の熱化、及
びしやへいあるいはトリチウム増殖をより効率的
にするための中性子増倍、等のブランケツト充填
材に必要とされる性質を簡便に兼ねそなえられる
トリチウム増殖材を提供する事にある。 Another object of the present invention is to easily provide the properties required for a blanket filler, such as thermalization of fast neutrons, and neutron multiplication to make desensitization or tritium multiplication more efficient. The objective is to provide a tritium breeder material that can be used as a tritium breeder.
即ち、この発明のトリチウム増殖材は、ペブル
を多層構造とし、リチウムを含まない物質から成
る適度な大きさの球状あるいは円柱状などの担体
上に、リチウム化合物又はリチウム含有合金から
成るトリチウム増殖物質を適度な厚さで、コーテ
イングして成る。このトリチウム増殖物質として
はLi2O、LiAlO2、Li2SiO3などの高融点物質が好
ましく、Li7Pb2、LiAlなどであつてもよい。担体
は、BeOのような高融点物質が好ましい。この様
な構造により生成トリチウムがすみやかに放出さ
れる程度に薄い増殖物質層と、熱除去用Heを大
量に流すに十分なペブル径の確保という両条件を
容易に実現する事が出来る。 That is, the tritium breeder material of the present invention has a multilayer pebble structure, and the tritium breeder material made of a lithium compound or a lithium-containing alloy is placed on a moderately sized spherical or cylindrical carrier made of a material that does not contain lithium. It is coated with a suitable thickness. The tritium breeding substance is preferably a high melting point substance such as Li 2 O, LiAlO 2 or Li 2 SiO 3 , and may also be Li 7 Pb 2 , LiAl or the like. The carrier is preferably a high melting point material such as BeO. With such a structure, it is possible to easily achieve both conditions: a growth material layer thin enough to quickly release generated tritium, and a pebble diameter sufficient to flow a large amount of He for heat removal.
以下この発明について実施例に基づき更に詳し
く説明する。 The present invention will be described in more detail below based on examples.
第１の実施例では、第１図に示すように直径20
mmの酸化ベリリウムBeO焼結体１の上に、厚さ５
mmの天然組成の酸化リチウムLi2O２を焼結コー
テイングして成る。この様なトリチウム増殖材に
おいて、Li2O層のLi中には92.5％の 7Liと7.5％
の 6Liが含まれる。融合反応で発生する中性子は
14.1MeVの運動エネルギを有するが、ブランケツ
ト内での各種反応、散乱により減速、変換され最
終的には熱エネルギに変換され発電等に用いられ
る。Li2O中のLiとの反応では中性子エネルギが
5MeV以上では 7Li（ｎ、n′α）Ｔ反応が著し
く、又、熱中性子〜0.5MeVでは 6Li（ｎ、α）
Ｔ反応が著しくこれら両者がトリチウム増殖に寄
与する。Li2O層内に生成されたＴは表面のごく
近傍で生成した少数が、反応の際の反跳により直
接表面から放出される外は、濃度勾配による拡散
で放出される。この実施例ではLi2O２の厚さが
５mmと十分薄いので、400℃以上の温度ではこの
拡散放出は十分速やかである。又、Ｄ−Ｔ融合反
応ではトリチウム１個の消費に対し１個の中性子
が発生されるのでトリチウム消費量に見合う量の
トリチウムを増殖する為には、発生中性子がＴ増
殖反応に完全に利用される必要があるが、現実に
は、必らず中性子損失があり、又融合炉の構造上
トリチウム増殖材で完全にプラズマを囲む事がむ
ずかしい場合もあるので、中性子増倍反応材が必
要とされている。上記の 7Li（ｎ、n′α）Ｔ反応
はトリチウム増殖と中性子増倍を兼ねるが、本実
施例の如く、担体としてBeOを用いるならば、
Be中に100％割合で存在する 9Beが1.9MeV以上
の中性子に対して 9Be（ｎ、2n） 8Be反応が著
しく、中性子増倍に利用できる。又、BeOは融点
が2570℃と非常に高く、高温での使用に耐える。
この例の増殖材は、ブランケツト内でも、中性子
スペクトルの硬い（高速中性子成分割合の多い）
プラズマに近い部分の増殖材に特に適当である。 In the first embodiment, the diameter is 20 mm as shown in FIG.
5mm thick beryllium oxide BeO sintered body 1
It is made of sintered coating of lithium oxide of natural composition Li 2 O 2 of mm. In such a tritium breeder material, Li in the Li 2 O layer contains 92.5% 7 Li and 7.5% Li.
Contains 6 Li. The neutrons generated in the fusion reaction are
Although it has a kinetic energy of 14.1 MeV, it is slowed down and converted by various reactions and scattering within the blanket, and is ultimately converted into thermal energy, which is used for power generation, etc. In the reaction with Li in Li 2 O, neutron energy is
Above 5 MeV, 7 Li (n, n'α) T reaction is significant, and at thermal neutrons ~ 0.5 MeV, 6 Li (n, α)
The T reaction is significant and both of these contribute to tritium multiplication. A small amount of the T produced in the Li 2 O layer is released directly from the surface due to recoil during the reaction, which is produced very close to the surface, and the rest is released by diffusion due to the concentration gradient. In this example, since the thickness of Li 2 O 2 is sufficiently thin at 5 mm, this diffusion release is sufficiently rapid at temperatures of 400° C. or higher. In addition, in the D-T fusion reaction, one neutron is generated for each tritium consumed, so in order to multiply tritium in an amount commensurate with the amount of tritium consumed, the generated neutron must be completely utilized in the T breeding reaction. However, in reality, there is always neutron loss, and it may be difficult to completely surround the plasma with tritium breeder material due to the structure of the fusion reactor, so a neutron multiplication reaction material is required. ing. The above 7 Li(n, n′α)T reaction serves both tritium multiplication and neutron multiplication, but if BeO is used as a carrier as in this example,
9 Be, which exists in 100% proportion in Be, exhibits a remarkable 9 Be (n, 2n) 8 Be reaction to neutrons of 1.9 MeV or higher, and can be used for neutron multiplication. In addition, BeO has a very high melting point of 2570°C and can withstand use at high temperatures.
The breeder material in this example has a hard neutron spectrum (high proportion of fast neutron components) even within the blanket.
It is particularly suitable for breeding materials in areas close to plasma.
第２の実施例では、第１図と同一構成部分につ
いては同一符号を用いて説明する。直径30mmのグ
ラフアイト球体１の上に、濃縮 6Liを用いて製造
した 6LiAlO2層２を厚さ５mm焼結コーテイング
して成る。この例ではLiAlO2層２のLiがトリチ
ウム増殖物質である。この例では担体１にグラフ
アイトを用いる事により高速中性子の減速により
6Li（ｎ、α）Ｔ反応を促進する。又、このグラ
フアイは中性子の外部への漏出を妨げる反射材、
しやへい材としての効果も著しい。この実施例
は、特にブランケツト内のプラズマから遠い部分
に使うのに好適である。又、トリチウムとグラフ
アイトとの反応による炭化水素の生成が問題とな
る場合にはグラフアイトを 6LiAlO2の層間に例
えばBeOやSiCのような別種物質層をもうければ
よい。なお上述した実施例ではトリチウム増殖物
質層の厚さを５mmとしたが、この発明は、この厚
さに限定されるものではない。又、担体の形状、
大きさもブランケツト方式によつて適当に選定さ
れるべきものである。又、担体としてMo、Nbな
どの金属を用いることも随意である。 In the second embodiment, the same components as those in FIG. 1 will be described using the same reference numerals. A graphite sphere 1 with a diameter of 30 mm is coated with a 5 mm thick sintered 6 LiAlO 2 layer 2 produced using concentrated 6 Li. In this example, Li in the LiAlO 2 layer 2 is a tritium breeding material. In this example, by using graphite for carrier 1, the speed of fast neutrons is reduced.
6 Li(n,α) Promotes T reaction. In addition, this graph eye is made of reflective material that prevents neutrons from leaking to the outside.
It is also very effective as a hardening material. This embodiment is particularly suitable for use in parts of the blanket that are far from the plasma. If the generation of hydrocarbons due to the reaction between tritium and graphite is a problem, a layer of another material such as BeO or SiC may be provided between the layers of graphite and 6 LiAlO 2 . In the above-described embodiment, the thickness of the tritium breeding material layer was 5 mm, but the present invention is not limited to this thickness. In addition, the shape of the carrier,
The size should also be appropriately selected according to the blanket method. It is also optional to use metals such as Mo and Nb as carriers.
又、この発明の他の実施例としては、担体層へ
のトリチウム蓄積を低減し本発明の効果を更に高
める為に、第２図に示すように担体１とトリチウ
ム増殖物質２との間に水素もしくは水が透過もし
くは溶解して固溶体を形成しにくい例えばBeOや
SiOのような物質の層３をもうけることも可能で
ある。またこの中間層３はＷ、Moなどの蒸着層
であつてもよい。 In another embodiment of the present invention, hydrogen is added between the carrier 1 and the tritium breeding material 2 as shown in FIG. Or, it is difficult for water to pass through or dissolve to form a solid solution, such as BeO.
It is also possible to provide a layer 3 of a material such as SiO. Further, the intermediate layer 3 may be a vapor-deposited layer of W, Mo, or the like.
以上述べた様に、この発明は、核融合炉ブラン
ケツト内に充填して用いられる固体状トリチウム
増殖材として、トリチウム増殖物質を含まない担
体上に、トリチウム増殖物質をコーテイングして
用いる事により、除熱用熱媒体、例えば高圧He
ガスの流動を困難にしない程度の大きさの粒径の
ペブルで、且つ生成トリチウムの放出が比較的速
やかである増殖物質厚さという相反する２条件を
容易に満すことが可能であり、且つ担体に適当な
物質を用いる事により中性子増倍、減速、しやへ
い等の役割をも容易に実現できるものである。 As described above, the present invention is capable of removing tritium by coating a tritium breeder material on a carrier that does not contain the tritium breeder material as a solid tritium breeder material to be filled in a fusion reactor blanket. Heat medium for heat, e.g. high pressure He
It is possible to easily satisfy the two contradictory conditions of pebble particles having a particle size that does not make gas flow difficult, and a growth material thickness that allows the release of generated tritium relatively quickly. By using an appropriate material for the carrier, roles such as neutron multiplication, moderation, and shielding can be easily realized.
第１図は本発明の実施例を示す断面図、第２図
は本発明の他の実施例を示す斜視断面図である。
１……担体、２……トリチウム増殖物質、３…
…水素、もしくは水の透過もしくは溶解しにくい
物質。
FIG. 1 is a sectional view showing an embodiment of the invention, and FIG. 2 is a perspective sectional view showing another embodiment of the invention. 1... carrier, 2... tritium breeding substance, 3...
...Hydrogen or a substance that is difficult to permeate or dissolve in water.
Claims (1)
チウム増殖物質を、このトリチウム増殖物質に比
べ中性子と反応してもトリチウムを生成しないか
もしくはその生成する量の少ない物質からなる担
体の表面に被覆したことを特徴とするトリチウム
増殖材。 ２ トリチウム増殖物質をリチウム元素の化合物
もしくはその合金としたことを特徴とする特許請
求の範囲第１項記載のトリチウム増殖材。 ３ トリチウム増殖物質を高融点物質としたこと
を特徴とする特許請求の範囲第１項記載のトリチ
ウム増殖材。 ４ トリチウム増殖物質をLi2O、LiAlO2、
Li2SiO3、Li7Pb2もしくはLiAlのうちの少なくと
も一種の物質としたことを特徴とする特許請求の
範囲第２項記載のトリチウム増殖材。 ５ 担体を14.1MeV以下のエネルギを有する中性
子との反応により２個以上の中性子を発生する元
素もしくはその化合物もしくはその合金としたこ
とを特徴とする特許請求の範囲第１項記載のトリ
チウム増殖材。 ６ 担体をベリリウム、モリブデンおよび鉛のう
ち少なくとも１種を含む化合物、合金もしくは金
属単体としたことを特徴とする特許請求の範囲第
１項記載のトリチウム増殖材。 ７ 担体を高融点物質としたことを特徴とする特
許請求の範囲第１項記載のトリチウム増殖材。 ８ 担体をBeOとしたことを特徴とする特許請求
の範囲第７項記載のトリチウム増殖材。 ９ 担体を中性子減速材としたことを特徴とする
特許請求の範囲第１項記載のトリチウム増殖材。 １０ 中性子減速材をグラフアイトもしくはSiC
のいずれかとしたことを特徴とする特許請求の範
囲第９項記載のトリチウム増殖材。 １１ 担体を水素もしくは水が透過もしくは溶解
して固溶体を形成しにくい物質としたことを特徴
とする特許請求の範囲第１項記載のトリチウム増
殖材。 １２ トリチウム増殖物質と担体との間に水素も
しくは水が溶解しにくい物質を介挿してなること
を特徴とする特許請求の範囲第１項記載のトリチ
ウム増殖材。 １３ 担体を球状もしくは円柱状としたことを特
徴とする特許請求の範囲第１項記載のトリチウム
増殖材。[Scope of Claims] 1. A tritium breeding material that reacts with neutrons to produce tritium is made of a carrier made of a material that does not produce tritium or produces less tritium when reacted with neutrons than the tritium breeding material. A tritium breeder material characterized by a coating on the surface. 2. The tritium breeding material according to claim 1, wherein the tritium breeding material is a compound of lithium element or an alloy thereof. 3. The tritium breeder material according to claim 1, wherein the tritium breeder material is a high melting point substance. 4 Tritium breeding materials are Li 2 O, LiAlO 2 ,
The tritium breeder material according to claim 2, characterized in that the material is at least one of Li 2 SiO 3 , Li 7 Pb 2 and LiAl. 5. The tritium breeder material according to claim 1, wherein the carrier is an element, a compound thereof, or an alloy thereof that generates two or more neutrons upon reaction with a neutron having an energy of 14.1 MeV or less. 6. The tritium breeder material according to claim 1, wherein the carrier is a compound, alloy, or simple metal containing at least one of beryllium, molybdenum, and lead. 7. The tritium breeder material according to claim 1, characterized in that the carrier is a high melting point substance. 8. The tritium breeder material according to claim 7, characterized in that the carrier is BeO. 9. The tritium breeder material according to claim 1, characterized in that the carrier is a neutron moderator. 10 Use graphite or SiC as neutron moderator
The tritium breeder material according to claim 9, characterized in that it is any one of the following. 11. The tritium breeder material according to claim 1, wherein the carrier is made of a material through which hydrogen or water is difficult to permeate or dissolve to form a solid solution. 12. The tritium breeding material according to claim 1, characterized in that a substance in which hydrogen or water is difficult to dissolve is interposed between the tritium breeding material and the carrier. 13. The tritium breeder material according to claim 1, wherein the carrier is spherical or cylindrical.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56061391A JPS57175986A (en) | 1981-04-24 | 1981-04-24 | Tritium breeder material |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56061391A JPS57175986A (en) | 1981-04-24 | 1981-04-24 | Tritium breeder material |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS57175986A JPS57175986A (en) | 1982-10-29 |
| JPS6256474B2 true JPS6256474B2 (en) | 1987-11-26 |
Family
ID=13169814
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56061391A Granted JPS57175986A (en) | 1981-04-24 | 1981-04-24 | Tritium breeder material |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS57175986A (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH06100676B2 (en) * | 1986-08-11 | 1994-12-12 | 川崎重工業株式会社 | Pebble for tritium production and tritium production equipment |
| JPH0695157B2 (en) * | 1986-08-11 | 1994-11-24 | 川崎重工業株式会社 | Tritium production equipment |
-
1981
- 1981-04-24 JP JP56061391A patent/JPS57175986A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS57175986A (en) | 1982-10-29 |
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