JPS6316716B2 - - Google Patents
Info
- Publication number
- JPS6316716B2 JPS6316716B2 JP54059054A JP5905479A JPS6316716B2 JP S6316716 B2 JPS6316716 B2 JP S6316716B2 JP 54059054 A JP54059054 A JP 54059054A JP 5905479 A JP5905479 A JP 5905479A JP S6316716 B2 JPS6316716 B2 JP S6316716B2
- Authority
- JP
- Japan
- Prior art keywords
- additives
- nuclear fuel
- tio
- sintered
- added
- 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
- 239000000654 additive Substances 0.000 claims description 28
- 239000003758 nuclear fuel Substances 0.000 claims description 23
- 229910010413 TiO 2 Inorganic materials 0.000 claims description 15
- 239000000203 mixture Substances 0.000 claims description 12
- 229910018072 Al 2 O 3 Inorganic materials 0.000 claims description 7
- 239000008188 pellet Substances 0.000 claims description 7
- 239000000463 material Substances 0.000 description 14
- OOAWCECZEHPMBX-UHFFFAOYSA-N oxygen(2-);uranium(4+) Chemical compound [O-2].[O-2].[U+4] OOAWCECZEHPMBX-UHFFFAOYSA-N 0.000 description 11
- FCTBKIHDJGHPPO-UHFFFAOYSA-N uranium dioxide Inorganic materials O=[U]=O FCTBKIHDJGHPPO-UHFFFAOYSA-N 0.000 description 11
- 238000005253 cladding Methods 0.000 description 8
- 239000013078 crystal Substances 0.000 description 7
- 230000007423 decrease Effects 0.000 description 7
- 239000000843 powder Substances 0.000 description 7
- 229910004298 SiO 2 Inorganic materials 0.000 description 6
- 230000000996 additive effect Effects 0.000 description 6
- 230000000694 effects Effects 0.000 description 6
- 238000010521 absorption reaction Methods 0.000 description 5
- ODINCKMPIJJUCX-UHFFFAOYSA-N calcium oxide Inorganic materials [Ca]=O ODINCKMPIJJUCX-UHFFFAOYSA-N 0.000 description 5
- CPLXHLVBOLITMK-UHFFFAOYSA-N magnesium oxide Inorganic materials [Mg]=O CPLXHLVBOLITMK-UHFFFAOYSA-N 0.000 description 5
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N Silicium dioxide Chemical compound O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 description 4
- LTPBRCUWZOMYOC-UHFFFAOYSA-N beryllium oxide Inorganic materials O=[Be] LTPBRCUWZOMYOC-UHFFFAOYSA-N 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- 239000000126 substance Substances 0.000 description 3
- KKCBUQHMOMHUOY-UHFFFAOYSA-N Na2O Inorganic materials [O-2].[Na+].[Na+] KKCBUQHMOMHUOY-UHFFFAOYSA-N 0.000 description 2
- GWEVSGVZZGPLCZ-UHFFFAOYSA-N Titan oxide Chemical compound O=[Ti]=O GWEVSGVZZGPLCZ-UHFFFAOYSA-N 0.000 description 2
- PNEYBMLMFCGWSK-UHFFFAOYSA-N aluminium oxide Inorganic materials [O-2].[O-2].[O-2].[Al+3].[Al+3] PNEYBMLMFCGWSK-UHFFFAOYSA-N 0.000 description 2
- 229910052681 coesite Inorganic materials 0.000 description 2
- 229910052593 corundum Inorganic materials 0.000 description 2
- 229910052906 cristobalite Inorganic materials 0.000 description 2
- 229910052751 metal Inorganic materials 0.000 description 2
- 239000002184 metal Substances 0.000 description 2
- 239000000377 silicon dioxide Substances 0.000 description 2
- 235000012239 silicon dioxide Nutrition 0.000 description 2
- 229910052682 stishovite Inorganic materials 0.000 description 2
- DLYUQMMRRRQYAE-UHFFFAOYSA-N tetraphosphorus decaoxide Chemical compound O1P(O2)(=O)OP3(=O)OP1(=O)OP2(=O)O3 DLYUQMMRRRQYAE-UHFFFAOYSA-N 0.000 description 2
- 229910052905 tridymite Inorganic materials 0.000 description 2
- 229910001845 yogo sapphire Inorganic materials 0.000 description 2
- 230000008094 contradictory effect Effects 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000002994 raw material Substances 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 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
- Inorganic Compounds Of Heavy Metals (AREA)
Description
〔発明の目的〕
（産業上の利用分野）
本発明は発電用原子炉において金属被覆管内に
密封して使用する酸化物系核燃料素子に関する。
（従来の技術）
発電用原子炉では、電力需要量に応じて出力を
自由に調節し得る負荷追従運転が可能であること
が経済的観点から強く要求されている。しかし原
子炉出力を急激に変化させると、酸化物系核燃料
素子を金属被覆管との熱膨脹率の差に起因して機
械的相互作用（以下PCMIという）が発生するこ
とが知られている。照射されて脆化している被覆
管は、PCMIが発生すると破損する場合があり、
被覆管内に蓄積された高放射能の核***生成物を
放出する。
このような事態に至るのを避ける目的で、現在
軽水炉等で採用されている対策は、原子炉の出力
変動条件を厳しく制限することによつてPCMIの
発生を最小限に抑制する方法である。これによつ
て発電用原子炉では燃料の破損を低減することに
成功している。
しかしこのように原子炉の運転条件に制限を設
ければ、当然のことながら所定の出力レベルまで
上昇させるのに時間を要し、プラント効率が低下
し、そのために大きな経済的損失をこうむること
となる。まして前述のような負荷追従運転は望む
べくもなく、より根本的な解決策を見出すことが
核燃料分野における急務となつている。
これを解決する１つの方法として添加物による
改善法がある。これは焼結ペレツト型酸化物系核
燃料素子にある種の添加物を加えることによつ
て、その高温における強度を低減し、通常の燃料
においてはPCMIがおこる条件下で使用しても、
被覆管に与える損傷を軽微なものとする方法であ
る。
酸化物系核燃料素子の添加物として特に有効な
ものは、Al2O3、BeO、CaO、MgO、SiO2、
Na2O、P2O5から選ばれた少なくとも２種類を含
む場合である。しかし被覆管の受ける損傷を無視
し得る程度まで改善するためには、最大５重量パ
ーセントまで添加する必要がある。
しかしながら核燃料物質の異物質の添加は、核
***性物質密度を低下させることになるので、そ
の添加量には制約がある。また中性子経済の観点
からも、添加物による中性子吸収をできる限り低
く抑えることが必要である。従つて少量の添加に
よつて所定の強度低下が達成できることが望まし
い。
（発明が解決しようとする問題点）
このように従来の酸化物系核燃料素子にあつて
は、Al2O3、BeO、CaO、MgO、SiO2、Na2O、
P2O5から選ばれた少なくとも２種類を含む添加
物を５重量パーセントまで添加すれば被覆管の損
傷をかなり緩和できるが、異物質の添加は核***
性物質密度を低下させるため添加量を少量に抑え
なければならないという相反した問題点があつ
た。
本発明はこの点に着目してなされたもので、
Al2O3、DeO、CaO、MgO、SiO2、Na2O、P2O5
から選ばれた少なくとも２種類の添加物を含む焼
結ペレツト型酸化物系核燃料素子に第３の組成物
（補助添加物）を加えることによつて、前記添加
物の必要添加量を低減し、核***物質の密度の低
下を抑え、中性子吸収を低く抑えた酸化物系核燃
料素子を提供することを目的とする。
〔発明の構成〕
（問題点を解決するための手段）
本発明の酸化物系核燃料素子にあたつては、
Al2O3、BeO、CaO、MgO、SiO2、Na2O5、
P2O5から選ばれた少なくとも２種類を添加物と
して含む焼結ペレツト型核燃料において、第３の
組成物としてTiO2を0.1重量パーセント以上1.0重
量パーセント以下添加している。
（作用）
このようなものにあつては、TiO2の少ない添
加量で核燃料素子の強度低減効果が得られるた
め、核***物質の密度の低下を抑え中性子吸収を
低く押えることができる。
（実施例）
以下に本発明を詳細に説明する。添加物の効果
は、これが核燃料物質母材の結晶粒界に介在する
ことによる核燃料素子の見掛上の強度低減効果を
狙つたものであり、このためには母材の結晶粒が
粒界に介在する添加物によつてできるだけ完全に
分離されていることが望ましい。逆に添加物は、
母材の結晶粒を分離するに十分なだけ添加する必
要がある。従がつて、できるだけ少ない量で所定
の効果を得るためには、母材の結晶程度を大きく
しておくのが有利である。何故ならば、焼結ペレ
ツト型核燃料の結晶粒の形状をモデル的に球形と
考えれば、単位体積当りの結晶粒界面積の総和は
結晶粒度に逆比例して減少することが簡単な計算
によつて求められるからである。また、結晶粒界
に介在する添加物の総量は、概略結晶粒界面積の
総和に比例すると考えられるからである。
一方、二酸化ウラン等の焼結ペレツト型酸化物
系核燃料では、ある種の組成物を添加すると、母
材の結晶粒が粗大化することが知られている。
本発明は以下の関係を組合わせることによつて
なされたもので、その特徴は第３の組成物を添加
することによつて、結晶粒を粗大化させ、第３の
組成物を添加するにもかかわらず、結果的にはよ
り少ない添加物量によつて焼結ペレツト型酸化物
系核燃料素子の高温強度低減の目的を達成するこ
とにある。
以下に具体的な実施例を用いて本発明の内容を
さらに詳述する。
二酸化ウラン粉末に対して組成比が重量パーセ
ントでSiO2：47、Al2O3：38、CaO：14.5、
Fe2O3：0.5の添加物をそれぞれ0.2、１、５重量
パーセント混合した後、2ton／cm2の圧力で圧縮し
直径12.5mm、高さ12.5mm〜13.7mmの成形体を得た。
これを1700℃中２時間焼結して密度95.3、94.6お
よび91.8％TDの３種の焼結体を得た。
一方上記添加物を同一ロツトの二酸化ウラン粉
末に1.0重量パーセント添加混合した後、さらに
TiO2微粉末をそれぞれ0.05、0.1、0.3、1.0、3.0
重量ベーセント添加混場して調整した５種類の原
料粉末を用いて、2ton／cm2の圧力で圧縮し、直径
12.5mm、高さ12.7〜13.1mmの成形体とした。これ
を1700℃で２時間焼結して、密度94.9、95.2、
95.8、96.1、および95.9％TDの焼結体を得た。
これら合計７種の焼結体について、切断し研摩
後常温から1200℃までの硬度を測定したところ第
１図および第２図に示す結果が得られた。
第１図からわかる通り前記組成比を有する添加
物を二酸化ウランに添加すると、二酸化ウラン焼
結体の強度は低下し、５重量パーセント添加の場
合に最大約60％の強度低下が得られる。しかし添
加量が１重量パーセントでは約35％の強度低下し
か得られない。
第２図からわかる通りTiO2を第３の組成物と
して加えた場合の効果は明らかである。すなわ
ち、TiO2を0.3％含有するものでは、添加物量が
１重量パーセントであつてもTiO2を含有しない
場合の５重量パーセント添加に相当する強度低下
が得られている。尚、TiO2添加量は第１図と第
２図の結果を比較すれば0.1％以上1.0％以下が最
適である。またTiO2＝0.05％以下あるいはTiO2
＝３％以上では逆に二酸化ウラン焼結体の強度を
増大させる作用をもつことがわかる。
またTiO2を加えたものではいずれの場合でも
平均結晶粒度が粗大化しており、これらを含まな
いものに比較してTiO2の場合で4.5〜6.0倍に成長
していることが観察された。この観察結果から、
結晶粒の粗大化による結晶粒界面積の減少が、結
果的に少量の添加物で所定の強度低下をもたらす
のに有効であることを示している。
以上詳述の通りAl2O3、BeO、CaO、MgO、
SiO2、Na2O、P2O5から選ばれた少なくとも２種
類の添加物を含む酸化物系核燃料素子に第３の組
成物たとえばTiO2等の結晶粒度を粗大化する材
料を添加することにより、PCMIが通常の核燃料
素子では発生する条件下でも被覆管に与える損傷
が少なく、かつ核***性物質の密度の低下が押え
られ、中性子吸収が少なくてすむなどの効果が得
られる。
また次のような実験も行なつた。二酸化ウラン
粉末に先の実施例記載のものと同一の組成比を有
する添加物、すなわちSiO2：47、Al2O3：38、
CaO：14.5、Fe2O3：0.5の添加物を1.0重量パーセ
ント添加後さらにTiO2微粉末及びNb2O5微粉末
をそれぞれ表１に示す割合で添加混合して調整し
た
[Object of the Invention] (Industrial Application Field) The present invention relates to an oxide-based nuclear fuel element that is used in a power reactor by being sealed in a metal cladding tube. (Prior Art) Power reactors are strongly required from an economic standpoint to be capable of load-following operation in which the output can be freely adjusted depending on the amount of electricity demanded. However, it is known that when the reactor output is suddenly changed, mechanical interaction (hereinafter referred to as PCMI) occurs due to the difference in coefficient of thermal expansion between the oxide nuclear fuel element and the metal cladding. Irradiated and brittle cladding may be damaged when PCMI occurs;
Releases highly radioactive fission products accumulated in the cladding. In order to avoid such a situation, the measures currently adopted in light water reactors, etc. are to minimize the occurrence of PCMI by strictly limiting the conditions for fluctuations in the reactor's output. This has successfully reduced fuel damage in power reactors. However, if limits are placed on the operating conditions of a nuclear reactor in this way, it will naturally take time to increase the output to a predetermined level, reducing plant efficiency and causing large economic losses. Become. Furthermore, the load-following operation described above is undesirable, and finding a more fundamental solution has become an urgent task in the field of nuclear fuel. One way to solve this problem is to use additives. This is done by adding certain additives to the sintered pellet type oxide nuclear fuel element to reduce its strength at high temperatures.
This method minimizes damage to the cladding. Particularly effective additives for oxide nuclear fuel elements include Al 2 O 3 , BeO, CaO, MgO, SiO 2 ,
This is a case where at least two types selected from Na 2 O and P 2 O 5 are included. However, in order to improve the damage to the cladding to a negligible extent, it is necessary to add up to 5% by weight. However, since the addition of foreign substances to nuclear fuel material reduces the density of fissile material, there are restrictions on the amount of foreign substances added. Also, from the viewpoint of neutron economy, it is necessary to suppress neutron absorption by additives as low as possible. Therefore, it is desirable that a predetermined strength reduction can be achieved by adding a small amount. (Problems to be Solved by the Invention) As described above, in conventional oxide nuclear fuel elements, Al 2 O 3 , BeO, CaO, MgO, SiO 2 , Na 2 O,
Damage to the cladding can be considerably alleviated by adding up to 5% by weight of additives containing at least two types selected from P 2 O 5 , but the addition of foreign substances reduces the density of fissile material, so the amount added should be kept small. There was a contradictory problem in that it had to be kept to a minimum. The present invention was made with attention to this point,
Al2O3 , DeO, CaO, MgO , SiO2 , Na2O , P2O5
By adding a third composition (auxiliary additive) to a sintered pellet type oxide-based nuclear fuel element containing at least two types of additives selected from, the required amount of the additive is reduced, The purpose of the present invention is to provide an oxide-based nuclear fuel element that suppresses a decrease in the density of fissile material and suppresses neutron absorption. [Structure of the Invention] (Means for Solving the Problems) In the oxide-based nuclear fuel element of the present invention,
Al 2 O 3 , BeO, CaO, MgO, SiO 2 , Na 2 O 5 ,
In the sintered pellet type nuclear fuel containing at least two types selected from P 2 O 5 as additives, TiO 2 is added as a third composition of 0.1 to 1.0 weight percent. (Function) In such a device, since the strength reduction effect of the nuclear fuel element can be obtained by adding a small amount of TiO 2 , it is possible to suppress a decrease in the density of the fissile material and suppress neutron absorption to a low level. (Example) The present invention will be explained in detail below. The effect of the additive is to reduce the apparent strength of the nuclear fuel element by intervening at the grain boundaries of the nuclear fuel material base material. It is desirable that they be separated as completely as possible by intervening additives. On the other hand, additives
It is necessary to add enough to separate the crystal grains of the base material. Therefore, in order to obtain the desired effect with as little amount as possible, it is advantageous to increase the crystallinity of the base material. This is because if the shape of the crystal grains of sintered pellet nuclear fuel is modeled as spherical, a simple calculation shows that the total grain boundary area per unit volume decreases in inverse proportion to the crystal grain size. This is because it is required. This is also because the total amount of additives present at grain boundaries is considered to be approximately proportional to the total sum of grain boundary areas. On the other hand, in sintered pellet-type oxide nuclear fuels such as uranium dioxide, it is known that when certain compositions are added, the crystal grains of the base material become coarse. The present invention was made by combining the following relationships, and its characteristics are that by adding the third composition, the crystal grains are coarsened; Nevertheless, the goal is to reduce the high temperature strength of the sintered pellet type oxide nuclear fuel element with a smaller amount of additives. The content of the present invention will be explained in further detail below using specific examples. The composition ratio in weight percent to uranium dioxide powder is SiO 2 : 47, Al 2 O 3 : 38, CaO: 14.5,
After mixing additives of 0.2, 1, and 5 weight percent of Fe 2 O 3 :0.5, the mixture was compressed at a pressure of 2 tons/cm 2 to obtain a molded body having a diameter of 12.5 mm and a height of 12.5 mm to 13.7 mm.
This was sintered at 1700° C. for 2 hours to obtain three types of sintered bodies with densities of 95.3, 94.6, and 91.8% TD. On the other hand, after adding 1.0% by weight of the above additive to the same lot of uranium dioxide powder,
TiO2 fine powder 0.05, 0.1, 0.3, 1.0, 3.0 respectively
Using 5 types of raw material powder prepared by adding weight basis, it was compressed at a pressure of 2 tons/cm 2 to reduce the diameter.
The molded body was 12.5 mm and 12.7 to 13.1 mm in height. This was sintered at 1700℃ for 2 hours, and the density was 94.9, 95.2,
Sintered bodies with TD of 95.8, 96.1, and 95.9% were obtained. A total of seven types of sintered bodies were cut and polished, and then the hardness was measured from room temperature to 1200°C, and the results shown in Figures 1 and 2 were obtained. As can be seen from FIG. 1, when an additive having the above composition ratio is added to uranium dioxide, the strength of the uranium dioxide sintered body decreases, and when 5 weight percent is added, the strength decreases by about 60% at maximum. However, when the amount added is 1% by weight, only about a 35% decrease in strength can be obtained. As can be seen from FIG. 2, the effect of adding TiO 2 as the third composition is clear. That is, in the case of a material containing 0.3% TiO 2 , even if the additive amount was 1% by weight, a decrease in strength equivalent to the addition of 5% by weight in the case of not containing TiO 2 was obtained. In addition, when comparing the results shown in FIG. 1 and FIG. 2, the optimum amount of TiO 2 to be added is 0.1% or more and 1.0% or less. Also, TiO 2 = 0.05% or less or TiO 2
= 3% or more, it can be seen that it has the effect of increasing the strength of the uranium dioxide sintered body. Furthermore, it was observed that the average crystal grain size became coarse in all cases with the addition of TiO 2 , and the growth was 4.5 to 6.0 times larger in the case of TiO 2 than in the case of those without these. From this observation,
This shows that reducing the grain boundary area by coarsening the grains is effective in reducing the strength to a certain level with a small amount of additives. As detailed above, Al 2 O 3 , BeO, CaO, MgO,
Adding a third composition, such as a material that coarsens the crystal grain size, such as TiO 2 to an oxide-based nuclear fuel element containing at least two types of additives selected from SiO 2 , Na 2 O, and P 2 O 5 . As a result, even under conditions where PCMI occurs in normal nuclear fuel elements, there is less damage to the cladding tube, the density of fissile material is suppressed, and neutron absorption is reduced. We also conducted the following experiments. Additives having the same composition ratio as those described in the previous example were added to the uranium dioxide powder, i.e., SiO 2 :47, Al 2 O 3 :38,
After adding 1.0% by weight of additives of CaO: 14.5 and Fe 2 O 3 : 0.5, TiO 2 fine powder and Nb 2 O 5 fine powder were added and mixed in the proportions shown in Table 1.
Al2O3、BeO、CaO、MgO、SiO2、Na2O、
P2O5から選ばれた少なくとも２種類の添加物を
含む焼結ペレツト型酸化物系核燃料素子に第３の
組成物TiO2を加えることによつて、前記添加物
の必要添加量を低減し、核***物質の密度の低下
を抑え、中性子吸収を低く抑えた酸化物系核燃料
素子を得ることができる。
Al2O3 , BeO, CaO, MgO , SiO2 , Na2O ,
By adding a third composition TiO 2 to a sintered pellet type oxide nuclear fuel element containing at least two types of additives selected from P 2 O 5 , the required amount of the additives is reduced. , it is possible to obtain an oxide-based nuclear fuel element in which the density of fissile material is suppressed and neutron absorption is suppressed to a low level.
第１図は各種含有率で添加物を加えた二酸化ウ
ラン焼結体の温度に対する硬度を示す特性図、第
２図は、添加物を１重量パーセント含有する二酸
化ウランにさらに各種含有率でTiO2を加えたも
のにつき焼結体の温度に対する硬度を示す特性
図、第３図は、添加物を１重量パーセント含有す
る二酸化ウランにさらに表１における含有率で
TiO2とNb2O5を同時に加えたものにつき焼結体
の温度に対する硬度を示す特性図である。
Figure 1 is a characteristic diagram showing the hardness versus temperature of uranium dioxide sintered bodies containing additives at various concentrations, and Figure 2 is a graph showing the hardness versus temperature of uranium dioxide sintered bodies containing additives at various concentrations . Figure 3 is a characteristic diagram showing the hardness versus temperature of the sintered body for uranium dioxide containing 1% by weight of additives, and the addition of uranium dioxide at the content rate in Table 1.
FIG. 3 is a characteristic diagram showing the hardness versus temperature of a sintered body in which TiO 2 and Nb 2 O 5 are added at the same time.
Claims (1)
P2O5から選ばれた少なくとも２種類を添加物と
して含む焼結ペレツト型核燃料において、第３の
組成物としてTiO2を0.1重量パーセント以上1.0重
量パーセント以下添加することを特徴とする酸化
物系核燃料素子。1 Al 2 O 3 , BeO, CaO, MgO, RiO 2 , Na 2 O 5 ,
A sintered pellet type nuclear fuel containing at least two types selected from P 2 O 5 as additives, characterized in that 0.1 to 1.0 weight percent of TiO 2 is added as a third composition. Nuclear fuel element.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP5905479A JPS55151292A (en) | 1979-05-16 | 1979-05-16 | Nuclear fuel element of oxide |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP5905479A JPS55151292A (en) | 1979-05-16 | 1979-05-16 | Nuclear fuel element of oxide |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS55151292A JPS55151292A (en) | 1980-11-25 |
| JPS6316716B2 true JPS6316716B2 (en) | 1988-04-11 |
Family
ID=13102221
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP5905479A Granted JPS55151292A (en) | 1979-05-16 | 1979-05-16 | Nuclear fuel element of oxide |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS55151292A (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| LU88668A1 (en) * | 1995-10-05 | 1997-04-05 | Euratom | Modified nuclear fuel to delay the development of the RIM effect |
| DE10115015C1 (en) * | 2001-03-27 | 2003-05-15 | Framatome Anp Gmbh | Process for producing a nuclear fuel sintered body |
-
1979
- 1979-05-16 JP JP5905479A patent/JPS55151292A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS55151292A (en) | 1980-11-25 |
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