CN113012827A - 一种抗水腐蚀氮化铀复合燃料芯块 - Google Patents
一种抗水腐蚀氮化铀复合燃料芯块 Download PDFInfo
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- 239000008188 pellet Substances 0.000 title claims abstract description 53
- 239000000446 fuel Substances 0.000 title claims abstract description 44
- MVXWAZXVYXTENN-UHFFFAOYSA-N azanylidyneuranium Chemical compound [U]#N MVXWAZXVYXTENN-UHFFFAOYSA-N 0.000 title claims abstract description 41
- 230000007797 corrosion Effects 0.000 title claims abstract description 38
- 238000005260 corrosion Methods 0.000 title claims abstract description 38
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 29
- 239000002131 composite material Substances 0.000 title claims abstract description 16
- 229910052751 metal Inorganic materials 0.000 claims abstract description 32
- 239000002184 metal Substances 0.000 claims abstract description 32
- 239000002245 particle Substances 0.000 claims abstract description 21
- 229910045601 alloy Inorganic materials 0.000 claims description 3
- 239000000956 alloy Substances 0.000 claims description 3
- 229910052790 beryllium Inorganic materials 0.000 claims description 2
- 229910052804 chromium Inorganic materials 0.000 claims description 2
- 150000002739 metals Chemical class 0.000 claims description 2
- 229910052758 niobium Inorganic materials 0.000 claims description 2
- 229910052726 zirconium Inorganic materials 0.000 claims description 2
- 230000001681 protective effect Effects 0.000 claims 1
- 239000003758 nuclear fuel Substances 0.000 abstract description 7
- 239000000498 cooling water Substances 0.000 abstract description 5
- 230000009286 beneficial effect Effects 0.000 abstract description 2
- 238000005253 cladding Methods 0.000 description 4
- 229910052770 Uranium Inorganic materials 0.000 description 3
- 229910001093 Zr alloy Inorganic materials 0.000 description 3
- 230000007547 defect Effects 0.000 description 3
- 230000003647 oxidation Effects 0.000 description 3
- 238000007254 oxidation reaction Methods 0.000 description 3
- 230000004992 fission Effects 0.000 description 2
- 229910052739 hydrogen Inorganic materials 0.000 description 2
- 239000001257 hydrogen Substances 0.000 description 2
- 238000002844 melting Methods 0.000 description 2
- 230000008018 melting Effects 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 2
- 229910000838 Al alloy Inorganic materials 0.000 description 1
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 1
- 229910001257 Nb alloy Inorganic materials 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 230000002950 deficient Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000004146 energy storage Methods 0.000 description 1
- 230000002708 enhancing effect Effects 0.000 description 1
- 238000004880 explosion Methods 0.000 description 1
- 150000002431 hydrogen Chemical class 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 239000007769 metal material Substances 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
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- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/60—Metallic fuel; Intermetallic dispersions
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- 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
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- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
本发明涉及核燃料芯块技术领域,具体地说是一种抗水腐蚀氮化铀复合燃料芯块,其特征在于:包括起保护作用的耐腐蚀金属体、分散在耐腐蚀金属体内的氮化铀颗粒。本发明与现有技术相比具有如下优势:1、通过耐腐蚀金属体将易与高温水、水蒸气发生反应的氮化铀燃料分隔开,提高了芯块暴露于高温冷却水或水蒸气时维持完整性的能力;2、芯块尺寸与现有燃料芯块一致,可装入现有反应堆燃料棒中,易于使用;3、适用于现役轻水反应堆,相比现役UO2燃料芯块或单相氮化铀燃料芯块具有较高的安全性,有利于消除PCI问题。
Description
技术领域
本发明涉及核燃料芯块技术领域,具体地说是一种抗水腐蚀氮化铀复合燃料芯块。
背景技术
轻水反应堆是核电站的主要堆型,目前所有的商业轻水堆都使用了UO2芯块或添加了Pu的U、Pu混合氧化物芯块作为燃料。
轻水反应堆的核燃料元件容易出现PCI问题,PCI是指水冷反应堆中使用的燃料芯块与包壳的相互作用。PCI是燃料棒破损的潜在因素之一,任其发展可导致包壳破损,因此PCI问题直接涉及到燃料元件在堆内使用的安全性。
UO2具有高熔点、高化学及辐照稳定性等优点。然而,UO2的热导率较低,在800℃时仅为约3.5W·m-1·K-1。因此,UO2燃料芯块的热量导出能力差,在反应堆运行时芯块的中心温度很高,在燃料芯块中会储存大量的热量。在事故工况下,在燃料芯块中储存的热量及裂变产物的衰变热会使锆合金包壳的温度迅速升高,继而使锆合金迅速与水蒸气发生氧化放热反应而产生大量热量和氢气,加速堆芯的熔毁并可能引发氢气爆炸。因此,提高燃料芯块的热导率,加强其热量导出能力是提升核燃料安全性的重要手段之一。
而氮化铀(UN)燃料,其中的铀金属密度达13.5gU/cm3,高于UO2的9.7gU/cm3,热导率也有20W·m-1·K-1左右。然而,氮化铀燃料相比UO2燃料也还有化学活性高、不耐高温水腐蚀的缺点。因此,解决氮化铀燃料在轻水堆中的腐蚀氧化是实现替代现有UO2燃料所必须解决的最重要问题。
发明内容
本发明的目的在于克服现有技术的不足,为轻水反应堆提供一种具有高热导率、高铀密度、且具有较强抗水腐蚀、抗蒸汽氧化性能的氮化铀燃料,降低现有氮化铀燃料在轻水堆中应用时的安全风险,替代现有的UO2燃料,提高反应堆安全性和经济性。
为实现上述目的,设计一种抗水腐蚀氮化铀复合燃料芯块,其特征在于:包括起保护作用的耐腐蚀金属体、分散在耐腐蚀金属体内的氮化铀颗粒。
进一步的,任意氮化铀颗粒均被耐腐蚀金属体包覆隔离。
进一步的,所述耐腐蚀金属体占芯块体积的10~30%,所述氮化铀颗粒占芯块体积的50~90%。
进一步的,所述氮化铀颗粒的粒径为50μm~1000μm。
进一步的,所述耐腐蚀金属体采用Be、Cr、Zr或Nb金属或上述金属的合金。
本发明与现有技术相比具有如下优势:
1、通过耐腐蚀金属体将易与高温水、水蒸气发生反应的氮化铀燃料分隔开,提高了芯块暴露于高温冷却水或水蒸气时维持完整性的能力;
2、芯块尺寸与现有燃料芯块一致,可装入现有反应堆燃料棒中,易于使用;
3、适用于现役轻水反应堆,相比现役UO2燃料芯块或单相氮化铀燃料芯块具有较高的安全性,有利于消除PCI问题。
附图说明
图1为本发明在一个实施例中的横截面示意图。图中氮化铀颗粒与耐腐蚀金属体的比例不代表实际的成分配比。
具体实施方式
现结合附图对本发明作进一步地说明。
实施例1
本例中氮化铀复合燃料芯块为外径8.192mm、高9.83mm的短圆柱形,具体为采用Zr合金的耐腐蚀金属体2,其占芯块体积的10%,其内分散有占芯块体积的90%、平均粒径为600μm和100μm的两种氮化铀颗粒1。参见图1,可见耐腐蚀金属体2呈现类似蜂窝状结构。
实施例2
本例中氮化铀复合燃料芯块为外径8.192mm、高9.83mm的短圆柱形,具体为采用占芯块体积30%的AlCr合金的耐腐蚀金属体2,其内分散有占芯块体积70%的平均粒径为200μm的氮化铀颗粒1。
实施例3
本例中氮化铀复合燃料芯块为外径8.192mm、高9.83mm的短圆柱形,具体为采用占芯块体积40%的Nb合金的耐腐蚀金属体2,其内分散有占芯块体积60%的平均粒径为200μm的氮化铀颗粒1。
实施例4
本例中氮化铀复合燃料芯块为外径8.192mm、高9.83mm的短圆柱形,具体为采用占芯块体积20%的Be-Al合金的耐腐蚀金属体2,其内分散有占芯块体积80%的平均粒径分别为1000μm、300μm、90μm的三种氮化铀颗粒1。
本发明与现有轻水堆使用的UO2燃料芯块相比,热导率大幅提升,可以用于解决现有UO2燃料芯块由于热导率低而导致的中心温度高、温度梯度大、储能大的缺点;而与直接由粉末烧结的单相氮化铀燃料芯块相比,本发明中易被高温冷却水腐蚀氧化的氮化铀被耐腐蚀的金属层分隔成了小块颗粒,即使金属层由部分缺陷或破损受冷却水腐蚀的区域也不易扩散至整个芯块,因此在燃料包壳破损后,本发明中的氮化铀复合芯块具有很强的维持完整性的能力,可大幅减少放射性裂变产物转移至一回路冷却水;
通过选用具有不同力学性能的金属材料作为金属层及调整金属层含量,实现在较大范围内调节本发明芯块的强度、蠕变等力学性质,有利于消除核燃料元件的PCI问题,提高燃料元件整体的安全性。
Claims (6)
1.一种抗水腐蚀氮化铀复合燃料芯块,其特征在于:包括起保护作用的耐腐蚀金属体(2)、分散在耐腐蚀金属体(2)内的氮化铀颗粒(1)。
2.如权利1所述的一种抗水腐蚀氮化铀复合燃料芯块,其特征在于:任意氮化铀颗粒(1)均被耐腐蚀金属体(2)包覆隔离。
3.如权利1所述的一种抗水腐蚀氮化铀复合燃料芯块,其特征在于:所述耐腐蚀金属体(2)占芯块体积的10~30%,所述氮化铀颗粒(1)占芯块体积的50~90%。
4.如权利1所述的一种抗水腐蚀氮化铀复合燃料芯块,其特征在于:所述氮化铀颗粒(1)的粒径为50μm~1000μm。
5.如权利1所述的一种抗水腐蚀氮化铀复合燃料芯块,其特征在于:所述耐腐蚀金属体(2)采用Be、Cr、Zr或Nb金属或上述金属的合金。
6.如权利1所述的一种抗水腐蚀氮化铀复合燃料芯块,其特征在于:所述耐腐蚀金属体(2)采用圆柱形。
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Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |
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