[1]盧志威,溫建,李雷,等.鋯合金涂層包殼專利申請(qǐng)態(tài)勢(shì)全景分析[J].中國(guó)材料進(jìn)展,2021,40(04):275-280.[doi:10.7502/j.issn.1674-3962.201912016]
LU Zhiwei,WEN Jian,LI Lei,et al.Analysis on Patents Application Situation of Coated Zirconium Alloy Cladding[J].MATERIALS CHINA,2021,40(04):275-280.[doi:10.7502/j.issn.1674-3962.201912016]
點(diǎn)擊復(fù)制
鋯合金涂層包殼專利申請(qǐng)態(tài)勢(shì)全景分析(
)
中國(guó)材料進(jìn)展[ISSN:1674-3962/CN:61-1473/TG]
- 卷:
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40
- 期數(shù):
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2021年第04期
- 頁(yè)碼:
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275-280
- 欄目:
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- 出版日期:
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2021-04-30
文章信息/Info
- Title:
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Analysis on Patents Application Situation of Coated Zirconium Alloy Cladding
- 文章編號(hào):
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1674-3962(2021)04-0275-06
- 作者:
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盧志威1; 2; 溫建1; 2; 李雷1; 2; 張顯生1; 2; 劉彤1; 2; 任啟森1; 2; 廖業(yè)宏1; 2
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(1. 中廣核研究院有限公司,廣東 深圳 518026)(2. 深圳核電站高安全性事故容錯(cuò)燃料技術(shù)工程實(shí)驗(yàn)室,廣東 深圳 518026)
- Author(s):
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LU Zhiwei1; 2; WEN Jian1; 2; LI Lei1; 2; ZHANG Xiansheng1; 2; LIU Tong1; 2; REN Qisen1; 2; LIAO Yehong1; 2
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(1. China Nuclear Power Technology Research Institute, Shenzhen 518026, China) (2. HighSafety ATF Engineering Laboratory of Shenzhen, Shenzhen 518026, China)
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- 關(guān)鍵詞:
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事故容錯(cuò); 涂層; 鋯合金; 包殼; 專利
- Keywords:
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accident tolerance; coating; zirconium; cladding; patent
- 分類號(hào):
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TL341;TG174.4
- DOI:
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10.7502/j.issn.1674-3962.201912016
- 文獻(xiàn)標(biāo)志碼:
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A
- 摘要:
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事故容錯(cuò)燃料(ATF)是日本福島核事故之后提出的新一代核燃料概念,主要是為了提高反應(yīng)堆在事故工況下的容錯(cuò)性能,從根本上提高核電廠對(duì)嚴(yán)重事故的抵御能力,從而有效地提高核電的安全性和經(jīng)濟(jì)性。針對(duì)傳統(tǒng)核燃料使用的鋯合金包殼,通過外表面涂層改性的方法提高其在事故工況下的抗高溫氧化性能是事故容錯(cuò)燃料的主要研究方向。為了對(duì)鋯合金涂層包殼的技術(shù)發(fā)展現(xiàn)狀和趨勢(shì)進(jìn)行全面了解,對(duì)該技術(shù)相關(guān)的國(guó)際及國(guó)內(nèi)專利申請(qǐng)態(tài)勢(shì)進(jìn)行了統(tǒng)計(jì)分析,研究了該領(lǐng)域的專利申請(qǐng)發(fā)展態(tài)勢(shì)、專利來源地區(qū)及布局地區(qū)特點(diǎn),重點(diǎn)分析了自20世紀(jì)60年代以來鋯合金涂層包殼技術(shù)分支發(fā)展趨勢(shì);此外,結(jié)合我國(guó)的鋯合金涂層包殼的研究現(xiàn)狀,從研究進(jìn)展及技術(shù)聚焦等方面提出鋯合金涂層包殼研發(fā)建議。
- Abstract:
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Accident tolerant fuel (ATF) is an advanced nuclear fuel concept proposed after the Fukushima nuclear accident in Japan which is mainly to improve the accident tolerance performance of reactors under accident conditions and fundamentally improve the ability of nuclear power plants to resist serious accidents, so as to effectively improve the safety and economy of nuclear power. For zirconium alloy cladding materials, improving the high temperature oxidation resistance by coating is the main direction under concept of accident tolerant fuel. In order to fully understand the technical development status and trend of zirconium alloy cladding, the international and domestic patent applications are statistically analyzed. In addition, the development trend of coated zirconium alloy cladding technology branch since 1960s is analyzed. In addition, according to the research and development status of zirconium alloy coating cladding in China, the suggestions on the research and development of zirconium alloy coating cladding are put forward from the aspects of research and development progress and technology focus.
備注/Memo
- 備注/Memo:
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收稿日期:2019-12-24修回日期:2020-01-15 基金項(xiàng)目:國(guó)家科技重大專項(xiàng)資助項(xiàng)目(2015ZX06004001)第一作者:盧志威,男,1985年生,高級(jí)工程師通訊作者:劉彤,女,1974年生,研究員級(jí)高級(jí)工程師, Email:liutong@cgnpc.com.cn
更新日期/Last Update:
2021-03-24