CN102842345A - 锝—99作为可燃毒物元件的应用 - Google Patents

锝—99作为可燃毒物元件的应用 Download PDF

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CN102842345A
CN102842345A CN201210340446XA CN201210340446A CN102842345A CN 102842345 A CN102842345 A CN 102842345A CN 201210340446X A CN201210340446X A CN 201210340446XA CN 201210340446 A CN201210340446 A CN 201210340446A CN 102842345 A CN102842345 A CN 102842345A
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technetium
burnable poison
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assembly
poison element
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于涛
谢金森
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Nanhua University
University of South China
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University of South China
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Abstract

本发明公开了锝—99的一种新用途,特别是在核反应堆中作为可燃毒物元件的应用。利用锝—99的中子吸收性能,将锝—99金属制成棒束状可燃毒物元件,布置在燃料组件中,制作成可燃毒物组件。一方面可起到压制过剩反应性的作用,另一方面可消耗锝—99,降低其长期放射性危害。

Description

锝—99作为可燃毒物元件的应用
技术领域
本发明涉及锝—99的一种新用途,特别是在核反应堆中作为可燃毒物元件的应用。
背景技术
目前,核动力反应堆均为裂变核能系统,利用铀、钚元素的裂变释放能量。铀、钚元素裂变所产生的裂变碎片及其衰变产物即裂变产物的种类有几百至上千种,其中有一部分裂变产物的半衰期非常长,可达104~107年,称为长寿命裂变产物,对环境特别是生物圈的潜在威胁极大,因此对长寿命裂变产物的妥善处置关系到裂变核能系统的可持续发展。锝—99是长寿命裂变产物中产量最高的一种核素,半衰期长达2.1×105年,一座1000MW级轻水堆运行一年卸出乏燃料中的锝—99可达20㎏。但锝—99在热中子能区与超热中子能区具有较大的中子吸收截面,锝—99吸收中子后的产物为锝—100,半衰期为15.8秒,衰变产物为稳定核素钌—100。而另一方面,核动力反应堆要满足一定的运行时间,初装料具有较大的剩余反应性,可燃毒物作为压制过剩反应性的一种手段广泛应用于目前的核动力反应堆当中。可燃毒物采用具有较大中子吸收截面的核素,吸收链式裂变反应中的过剩中子,实现过剩反应性的压制,目前用于可燃毒物的核素主要有硼、铒、钆,还未见将锝—99用作可燃毒物核素的新技术。
发明内容
本发明的目的是提供锝—99的一种新用途,特别是在核反应堆中作为可燃毒物元件的应用。将锝—99金属制成棒束状可燃毒物元件,布置在燃料组件中,制作成可燃毒物组件。
本发明提供锝—99作为可燃毒物元件的应用,先将锝—99金属切削成直径7.5~8.5㎜、高12~13㎜的圆柱形金属块,再将锝—99金属块叠放入锆四合金包壳中,用弹簧压紧后,包壳两端口用端塞密封固定,构成锝—99可燃毒物元件,其中锝—99金属块的多少依据核反应堆活性区高度大小调节,圆柱形锝—99金属块外径与锆四合金包壳内径间留有0.2㎜气隙,根据反应性控制及组件功率分布的要求,选用相应数量的锝—99可燃毒物元件布置在可燃毒物组件中。
本发明利用锝—99的中子吸收性能,将锝—99作为可燃毒物元件布置在燃料组件中,一方面可起到压制过剩反应性的作用,另一方面可消耗锝—99,降低其长期放射性危害。不同数量锝—99可燃毒物元件布置的可燃毒物组件,在不同的锝—99含量下对过剩反应性控制的效果见图5所示。在8根、12根、16根锝—99可燃毒物元件情况下,对过剩反应性的控制能力最大分别可达0.0470(△k∕k)、0.0696(△k∕k)、0.0920(△k∕k),满足核反应堆可燃毒物的过剩反应性控制能力。不同锝—99可燃毒物元件数量、不同锝—99百分含量下组件的无限增殖系数如下:
Figure 201210340446X100002DEST_PATH_IMAGE001
附图说明
图1为锝—99可燃毒物元件结构示意图;
图2为内含8根锝—99可燃毒物元件的可燃毒物组件布置图;
图3为内含12根锝—99可燃毒物元件的可燃毒物组件布置图;
图4为内含16根锝—99可燃毒物元件的可燃毒物组件布置图;
图5为可燃毒物组件无限增殖系数随锝—99含量的变化曲线图。
具体实施方式
如图1所示,先将锝—99金属切削成直径7.5~8.5㎜、高12~13㎜的圆柱形金属块4,再将锝—99金属块4叠放入圆筒形锆四合金包壳3中,用弹簧2压紧后,包壳3两端口分别用上端塞1、下端塞5密封固定,构成锝—99可燃毒物元件,包壳3起到包容放射性物质的作用,其中锝—99金属块4的多少依据核反应堆活性区高度大小调节,圆柱形锝—99金属块4外径与锆四合金包壳3内径间留有0.2㎜气隙,以容纳锝—99金属块4在反应堆运行温度下的膨胀及受中子辐照后的膨胀,根据反应性控制及组件功率分布的要求,选用相应数量的锝—99可燃毒物元件布置在可燃毒物组件中,如图2、图3、图4分别为内含8根、12根、16根锝—99可燃毒物元件的可燃毒物组件布置图,图中6为锝—99可燃毒物元件,7为组件导向管,8为中子测量通道,9为核燃料元件。

Claims (1)

1.锝—99作为可燃毒物元件的应用。
CN201210340446XA 2012-09-14 2012-09-14 锝—99作为可燃毒物元件的应用 Pending CN102842345A (zh)

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Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104700905A (zh) * 2015-02-17 2015-06-10 上海核工程研究设计院 一种载硼整体型和离散型组合可燃毒物燃料组件
WO2023077687A1 (zh) * 2021-11-05 2023-05-11 中广核研究院有限公司 燃料棒、燃料组件及其反应堆堆芯

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN87105267A (zh) * 1986-08-01 1988-02-17 株式会社日立制作所 燃料组件和核反应堆
JPH06138272A (ja) * 1992-10-30 1994-05-20 Toshiba Corp 燃料集合体
US20030156675A1 (en) * 2000-02-24 2003-08-21 Francesco Venneri System and method for radioactive waste destruction
CN102332315A (zh) * 2007-09-26 2012-01-25 大亚湾核电运营管理有限责任公司 压水堆核电站反应堆堆芯燃料组件换料方法

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN87105267A (zh) * 1986-08-01 1988-02-17 株式会社日立制作所 燃料组件和核反应堆
JPH06138272A (ja) * 1992-10-30 1994-05-20 Toshiba Corp 燃料集合体
US20030156675A1 (en) * 2000-02-24 2003-08-21 Francesco Venneri System and method for radioactive waste destruction
CN102332315A (zh) * 2007-09-26 2012-01-25 大亚湾核电运营管理有限责任公司 压水堆核电站反应堆堆芯燃料组件换料方法

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104700905A (zh) * 2015-02-17 2015-06-10 上海核工程研究设计院 一种载硼整体型和离散型组合可燃毒物燃料组件
WO2023077687A1 (zh) * 2021-11-05 2023-05-11 中广核研究院有限公司 燃料棒、燃料组件及其反应堆堆芯

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