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CN102203879A - 高热传导率核燃料包壳及其制备工艺 - Google Patents

高热传导率核燃料包壳及其制备工艺 Download PDF

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CN102203879A
CN102203879A CN200980136879XA CN200980136879A CN102203879A CN 102203879 A CN102203879 A CN 102203879A CN 200980136879X A CN200980136879X A CN 200980136879XA CN 200980136879 A CN200980136879 A CN 200980136879A CN 102203879 A CN102203879 A CN 102203879A
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nuclear fuel
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fuel cladding
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CN102203879B (zh
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朱利安·卡贝内罗
勒内·帕耶
法比安·奥迪贝尔
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Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
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Abstract

本发明涉及一种全部或部分由陶瓷基质复合材料制成的核燃料包壳,所述陶瓷基质复合材料包括碳化硅SiC基质增强纤维以及位于所述基质和纤维之间的界面层,所述基质由至少一种选自碳化钛TiC、碳化锆ZrC或者碳硅化钛Ti3SiC2的碳化物组成。当在温度800℃-1200℃范围内受到辐射时,上述包壳可将核燃料机械维持于其中,同时使产生的热能最优地向冷却气体传递。本发明还涉及制备该核燃料包壳的方法。

Description

高热传导率核燃料包壳及其制备工艺
技术领域
本发明涉及核燃料领域,尤其涉及氦冷“高温”核反应堆的核燃料包壳,及其制备工艺。
背景技术
未来的核反应堆之中,那些快速中子反应堆(FNR),其以氦作为冷却气体(即所谓″He-GFR″反应堆),可能被涉及。这个反应堆就是所谓的“高温”反应堆,因为在操作期间它的核心温度通常在800℃-1200℃之间的范围变化。
如专利申请EP1 913 600所描述的那样,用于此类反应堆中的核燃料包壳可以是平板、圆柱、球体或空腔网的形式。
当面对上述温度条件时,包壳需要使用高熔点的难熔材料(为了保证足够的热机械稳定性以便将燃料维持在包壳里面)还应该在辐射条件下具有高热传导率(以便在核反应堆运行时最优地向冷却气体传导所产生的热能)
陶瓷虽然满足这些标准,但是陶瓷太易碎而不能承受核燃料包壳的操作条件。
事实上,核燃料中的裂变反应会产生固态及气态的裂变产物,使得包壳膨胀。当受到如此的重荷时,构成燃料包壳的陶瓷可能会断裂且造成燃料外泄。
为避免此类外泄,使用SiCf/SiC型陶瓷基质复合材料(CMC)会是很有益的,以改善材料机械性能。这样的材料通常是具有二维或三维空间排列的硅碳化物纤维(称为SiCf),其可以强化其所结合的SiC陶瓷基体。
然而,在给定温度下,SiCf/SiC型CMCs的热传导率可能会受到辐射条件的影响而急剧下降。
因此在“He-GFR”核反应堆高温运行时,采用CMCs从核燃料包壳向冷却气体传递热量是不合适的。
发明内容
本发明的一个目的是提供一种核燃料包壳,其全部或部分由复合材料构成,在800℃-1200℃温度辐射下,其具有足够的机械强度以将燃料保持在包壳里面,同时使产生的热能最优地向冷却气体传递。
因此,本发明的主题涉及全部或部分由陶瓷基质复合材料制成的核燃料包壳,其包括用于增强所述基质的碳化硅(SiC)纤维、以及在基质和纤维之间的界面层,所述基质至少包含下列一种碳化物,碳化钛TiC、碳化锆ZrC或硅碳化三钛Ti3SiC2
如下所述:当被辐射且温度在800℃-1200℃时(优选800℃-1000℃,或等于800℃),基于本发明的核燃料包壳的热传导性使得冷却气体传导热量得以改善,同时,保留了热机械性(高熔点)和机械性(脆性降低)的特点,这是CMSs固有的特性,并且可以使得燃料很好地受限于包壳中。
基于优选实施例,陶瓷基质合成材料进一步包括碳化硅SiC。因此,以基质体积计,例如,碳化硅SiC的量少于50%(通常,1%-50%),优选少于25%(通常,1%-25%),更优选少于10%(通常,1%-10%)。添加不同量的SiC可使得基质的特性(例如热传导性)被优化以适于常规工况。将SiC结合入基质可提高其与SiC纤维的热机械兼容性:例如,基质和纤维之间热膨胀系数的契合可降低膨胀效果差异(膨胀差会导致核燃料包壳断裂)。
在优选实施例中,以基质体积计,碳化硅SiC在基质中的体积比例为5%-15%(特别是基质包含TiC时)。出人意料的是,如下所示,这样一个基质组成使得它能够达到最优的热传导率。
可选择的,这样的基质具有圆柱形微观结构。
对于纤维,它们可能是全部或者部分有序排列好的。因此,它们通常来源于预成型的纤维,其通常由纤维制成且被定向排列而非随意排列。因此,纤维可具有如下形态,二维编织(比如:辫子),伪二维编织(例如随后被缝制的编织物),三维编织,针织物或毡类。
优选的,核燃料包壳为管形或平板型时纤维分别为辫形或毡形。
由于其良好的中子稳定性和热稳定性,本发明中纤维由SiC制成,以便更适于本发明环境。
此外,纤维和基质之间还设有界面层。
这一界面层可能完全或者部分由一种具有几个叠层的化合物构成,比如,优选热解碳。
这些层的重叠性可能是:
-由化合物固有结构所导致(即因为此化合物天然具有此结构,比如裂解碳,裂解碳是由石墨平面组成,此种结构被称为板层);
-从化合物制备过程中得到(此种过程可为下文所述的脉冲CVI工艺:此结构被称为多层结构)
界面层平均厚度为10nm-500nm,优选10nm-50nm,更优选10nm-30nm,随厚度的降低机械特性提升。
构成基于本发明的核燃料包壳的复合材料的多孔性以体积计不高于10%(甚至5%)以便促进高热传导性。
本发明的另一目的是,通过此项发明提供一套制备核燃料包壳的工艺方法。这项工艺包括基于如下工艺步骤制备复合材料:
a)利用纤维制备纤维预制件,
b)通过化学气相沉积将上述界面层沉积到所述纤维预制件,
c)通过化学气相沉积将基质沉积到涂覆有界面层的纤维预制件上。
这种纤维预制件的几何结构通常与将要制备的核燃料包壳的结构近似。本发明的制备工艺完成后,此包壳结构基本与最终形式一致或最多再需要一些打磨操作。
优选的,步骤c)的化学气相沉积使用前体混合物,所述前体混合物包括i)至少一种选自钛基,锆基或者硅基的化合物;ii)一种碳氢化合物和iii)氢。
更优选的,所述前体为:
-钛化合物为至少一种选自TiCl4、TiBr4或Ti[CH2C(CH3)3]4的化合物,
-锆化合物为至少一种选自ZrCl4、ZrBr4或Zr[CH2C(CH3)3]4的化合物,
-硅化合物为至少一种选自SiCl4、SiH2Cl4或CH3SiCl3的化合物,
-碳氢化合物为至少一种化合物选自CCl4H2、CH4、C4H10或C3H8的化合物。
优选的,至少有一个化学气相沉积(即,基于步骤b)沉积界面层,或者基于步骤c)沉积基质)是脉冲型。
本发明其它目标、特性和益处基于下述非限制性实施例的描述而更清晰。
附图说明
图1显示随SiC比例变化TiC基陶瓷材料热传导性变化,此为温度函数。
图2显示在800℃辐射下TiC基陶瓷材料热传导性变化,此为SiC比例的函数。
具体实施方式
下面举例说明本发明的制备工艺部分,其中用于核燃料包壳组合物的陶瓷基质复合材料(CMC),被制备。
基于前述,基于本发明,在制备程序的最后使用具有与核燃料包壳(例如)形状和尺寸相近或相同的纤维预制件,可得到毛坯型或最终型包壳。
这些实施例在辐射前和辐射后表征陶瓷材料(不包括纤维和界面层)的热特性,这代表所制备的CMC。
1-制备用于本发明的核燃料包壳组合物的陶瓷基质复合材料(CMC)
下述制备操作采用本领域技术人员公知的工艺,即,化学气相沉积工艺,所谓CVI。
使用CVI,碳化物通过前体形成,并被沉积到纤维预制件。这种前体通常为气态。
一种特殊类型的CVI为脉冲CVI,例如EP0 385 869或″T.M.Besmann,Ceram.Trans.,Vol 58,第1页-12,1995″所描述的。
在脉冲CVI中,前体在反应容器中通过脉冲序列被输送(比如在烤箱中)。每一次脉冲,前体在容器中的压力通过下面的三种相态,随着时间的变化而变化:
-相态1:增大压力至工作压力(一般为几个千帕),以导入前体;
-相态2:维持工作压力(碳化物沉积的阶段);
-相态3:降低压力,以排出过量前体。
1.1-制备SiC f /TiC类型的CMC
使用CVI工艺,由碳化硅SiC有序纤维制备的纤维预制件被界面层包裹,所述界面层平均厚度为几十纳米到几百纳米,其由板层化合物组成,比如热解碳(PyC)。
纤维预制件然后被置于1050℃、热壁且初级真空的烤箱中。
随后,使用CVI脉冲,在5kPa工作压力下,CMC基质通过起始于容置在40kPa压力下混合物容器中的气态前体TiCl4,CH4和H2经气相反应而得的钛碳化物TiC沉积而成。
为了尽可能得到均匀的碳化物沉积物,在组成和微观结构层面,优选在低温(通常为900℃-1200℃)和低工作压力(通常为1kPa-10kPa)下工作以便限制沉积速率。
应该指出,除温度和压力外其它参数也会影响碳化物沉积的均质性。特别是,碳氢化合物的性质,碳比例和稀释因子。
因此,例如,TiC沉积:
-碳的比例,mC/Ti,相当于前体气态混合物中碳原子与钛原子数量比,虽然其变化为所用碳氢化合物的函数,但是一般必须保持在1-18的范围内;
-稀释因子α相当于前体总浓度与TiCl4的浓度(摩尔/升)之比,(或者α=([TiCl4]+[CH4]+[H2])/[TiCl4]),但是一般必须保持在15-100的范围内。
载体气体(CH4,尤其是H2)的流速,控制TiCl4沸点,使得TiCl4流速、稀释因素α和碳比例mC/Ti可控。
烤箱内压力也是基于流速以及截流阀的开启时间的。
在当前状态下,沉积参数如下:
-载体气体的平均流速=30L/h
-截流阀的开启时间(相态1)=0.2-0.3秒
-滞留时间(相态2)=4-5秒
-泵浦时间(相态3)=1秒
-每次脉冲沉积厚度=1.5nm
-α=50
-mC/Ti=9
-沉积速率=大约1μm/h
SiCf/TiC类型的CMC就是这样得到的,在CMC中,基质是根据一定化学计量比的TiC得到的,并且具有柱形的微型结构和平均40μm的厚度。
1.2-制备SiC f /ZrC类型的CMC
操作条件同上述例子中描述的条件类似,同样可以用来准备制作CMC。在CMC中基质由碳化锆ZrC构成,特别参数设置如下:
-ZrCl4,C3H6,H2气体以及氩气Ar具有相等的量1600℃/mC/Zr=0.5(沉积速率不到14μm/h);或者
-ZrBr4,CH4,H2,Ar/1000℃-1500℃/1-10kPa.
1.3-制备SiC f /TiC-SiC类型的CMC
在此情况下,所制备的CMCs的基质是混合组合物,由碳化钛TiC和碳化硅SiC组成。
由于脉冲CVI特别适于制备混合基质,这是因其可通过改变例如脉冲的数量(此为每个碳化物前体的函数)而轻易改变TiC-SiC比例,所以它能很好地用来制备混合的基质。这种特性已经用来准备制作三混SiCf/TiC-SiC陶瓷基质复合材料,其中基质如下以体积计TiC/SiC组分:90/10,75/25,50/50。
一些脉冲CVI沉积形态已被考虑。
在实施例1中,在TiC和SiC沉积层序的脉冲数被减少使得沉积层不连续。
TiC的沉积条件如前述。
对于SiC沉积,除以下参数外,沉积条件与TiC的沉积条件相似:
-气态前体:氢气和MTS(甲基三氯硅烷,分子式CH3SiCl3)
-温度从900℃到1050℃
-工作压力从1.5kPa到5kPa
SiC(PH2/PMTS)从1/4到5(从1/4到1/2,残留的碳原子会形成,当超过3的时候,就不会有再多的残留碳原子。但是,沉积速率会随着αSiC的增大而增大)。
应当注意的是SiC层的沉积速率与上述温度和压力值是成比例的。
当前状态下,下述参数有效地用于SiC沉积:
-温度=1050℃
-工作压力=4kPa
SiC(PH2/PMTS)=0.5
-每次脉冲平均沉积厚度=3nm
-沉积速率大约为0.3-1μm/h
脉冲序列结构如下:2次脉冲用于TiC沉积然后1次脉冲用于SiC沉积。
最后得到的混合基质是由一定化学计量比的SiC和TiC组成的,平均厚度为40μm。
在实施例2中,进行纳米测序沉积,即不同特性的沉积层具有平均10-100nm的厚度,并且连续沉积。为了达到目的,前体脉冲有目的地针对TiC或SiC连续产生(比如,40次脉冲对SiC和80次脉冲对TiC,或者20次脉冲对SiC和40次脉冲对TiC)。
在实施例3中,SiC和TiC前体一起导入。通常,前体和操作条件从以下列条件中选择:
-TiCl4,SiCl4,CCl4H2/950°-1150℃/100kPa
-TiCl4,SiCl4,C3H8,H2/950°-1150℃/4-40kPa
-TiCl4,SiCl4,CH4,H2/950°-1150℃/7kPa
-TiCl4,SiH2Cl4,C4H10,H2/950°-1150℃/100kPa
-TiCl4,CH3SiCl3,H2/950°-1150℃/1kPa-100kPa
-TiCl4,SiCl4,C3H8,H2/950°-1150℃/100kPa
2-含有TiC的陶瓷基质复合材料的热特性
陶瓷材料(没有纤维和界面层),同前面四种TiC基的CMCs基质组成相同,通过在一定压力下烧结制成。
这四种陶瓷材料的TiC/SiC组成体积比例分别是:100/0,90/10,75/25,50/50。
这些陶瓷材料使得四种先前制备的TiC基陶瓷基质复合材料的相对的热传导率可被测定,虽然它们的热传导率的绝对值与相应的陶瓷基质复合材料不同,但是它们的相对值是具有可比性的。在其它方面,这些陶瓷材料彼此间热传导率是相似的并可指示四种之前制备的陶瓷基质复合材料的相关特性。
实际上,对这种陶瓷材料的热扩散率在不同的温度下进行了测量。
给定这些陶瓷材料的密度和质量热容量(记作Cp),热传导率可以通过以下公式进行计算κ=αρCp,其中
-κ为热传导率(W.m-1.K-1)
-α为热扩散率(m2.s-1)
-ρ为密度(kg.m-3)
-Cp为质量热容量(J.kg-1.K-1)
适用于TiC和SiC的Cp(T)计算公式如下:
C p ( SiC ) = 925.65 + 0.3772 T - 7.9259 × 10 - 5 T 2 - 3.1946 × 10 7 T 2
(温度T为开尔文温度K)
Cp(TiC)=0.7415+0.00114T-1.57655×10-6T2+1.14714×10-10T3+7.05467×10-13T4
(温度T为开尔文温度K)
当陶瓷材料为混合组分时(例如75%的TiC+25%的SiC),它的质量热容量为每种碳化物的加权平均值
通过计算,可以得到热传导率的变化(曲线趋势)为所得温度的函数,如图1所示。
从图1可以得出,随着碳化钛TiC在基质中加入量的增加,未辐射过的SiCf/TiC-SiC类型的CMC的热传导率会随之增加,而与温度改变无关,尤其是在温度为800℃-1200℃、Ti含量超过50%时更不会改变。
下面热传导率的测算已经证实了陶瓷材料在辐射后的这一特性。
这些测定是通过相同程序对五种受辐射陶瓷材料进行的,即四种前述陶瓷材料和一种由100%SiC组成的陶瓷材料(也就是,如下陶瓷材料中TiC/SiC比例分别为:100/0,90/10,75/25,50/50,0/100)
在模拟中子流中的放射性是通过输入Kr离子而形成的,所述Kr离子能量可以达到74MeV以便达到1dpa(每原子位移)的辐射量,以便形成形成两个损伤区域,即,一个为核子的交互区(模拟中子损伤),另一个为电子交互区。热传导率是在800℃的核子交互区内测得的。
结果如图2所示。表明由TiC和SiC组成的陶瓷材料在800℃辐射时的热传导率,会随着TiC比例的提高而增加。这些陶瓷材料组成的体积比例为90%的TiC和10%的SiC(有代表性的材料是TiC组成在95%-85%之间,其余部分为SiC,以体积计)甚至发现具有最优的热传导率。
另有结果表明,在Au离子辐射后(4Me V,8dpa),TiC制作的陶瓷材料在温度800℃时热传导率比SiC制作的陶瓷材料的热传导率更优良。
由此可知,为制备核燃料包壳,使用包括由SiC纤维、界面层和至少一种选自碳化钛TiC、碳化锆ZrC或者三元化物碳硅化钛Ti3SiC2的碳化物组成的基质的陶瓷基质复合材料,可以使得所述包壳在800℃-1200℃、辐射下热传导率提高。
在″He-GFR″反应堆运行过程中,本发明的核燃料包壳可机械的维护核燃料并且保证向冷却气体传导热量,其效率高于由SiCf/SiC类型的CMC制作的包壳。

Claims (15)

1.一种全部或部分地由陶瓷基质复合材料制成的核燃料包壳,所述陶瓷基质复合材料包括用于增强所述基质的碳化硅SiC纤维以及位于所述基质和纤维之间的界面层,所述基质由至少一种选自碳化钛TiC、碳化锆ZrC或者碳硅化钛Ti3SiC2的碳化物组成。
2.根据权利要求1所述的核燃料包壳,其中所述基质进一步包括碳化硅SiC。
3.根据权利要求2所述的核燃料包壳,其中以基质体积计碳化硅SiC含量小于25%。
4.根据权利要求3所述的核燃料包壳,其中以基质体积计碳化硅SiC含量小于10%。
5.根据权利要求3所述的核燃料包壳,其中以基质体积计碳化硅SiC含量为5%-15%。
6.根据前述任一权利要求所述的核燃料包壳,其中所述基质具有圆柱形微观结构。
7.根据前述任一权利要求所述的核燃料包壳,其中所述纤维全部或部分地呈有序排列。
8.根据前述任一权利要求所述的核燃料包壳,其中所述界面层全部或部分地由具有叠层的化合物组成。
9.根据前述任一权利要求所述的核燃料包壳,其中所述界面层的平均厚度为10nm-500nm。
10.根据前述任一权利要求所述的核燃料包壳,其中以体积计所述复合材料的孔隙率不大于10%。
11.一种制备权利要求1-10所述的核燃料包壳的工艺,其包括如下步骤:
a)由所述纤维制备纤维预制件;
b)通过化学气相沉积把所述界面层沉积到所述纤维预制件上;
c)通过化学气相沉积把所述基质沉积到被界面层包裹的纤维预制件上。
12.根据权利要求11所述的制备工艺,其中所述步骤c)的化学气相沉积使用一种前体混合物,所述前体混合物包括i)至少一种选自Ti-,Zr-或者Si-基的化合物ii)碳氢化合物iii)氢。
13.根据权利要求12所述的制备工艺,其中:
-所述钛化物至少选自下述化合物中的一种:TiCl4,TiBr4或者Ti[CH2C(CH3)3]4
-所述锆化物至少选自下述化合物中的一种:ZrCl4,ZrBr4或者Zr[CH2C(CH3)3]4
-所述硅化物至少选自下述化合物中的一种SiCl4,SiH2Cl4或者CH3SiCl3
14.根据权利要求12或13所述的制备工艺,其中所述碳氢化合物至少选自下述化合物中的一种CCl4H2,CH4,C4H10或者C3H8
15.根据权利要求11-14中任一所述的制备工艺,其中至少一个所述化学气相沉积是脉冲类型。
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