天堂国产午夜亚洲专区-少妇人妻综合久久蜜臀-国产成人户外露出视频在线-国产91传媒一区二区三区

當前位置:主頁 > 科技論文 > 化學工程論文 >

用于高溫氣冷堆的核石墨(英文)

發(fā)布時間:2018-03-14 20:48

  本文選題:核石墨 切入點:高溫氣冷堆 出處:《新型炭材料》2017年03期  論文類型:期刊論文


【摘要】:自1942年首次在CP-1反應堆中使用以來,核石墨因其優(yōu)異的綜合性能,在核反應堆特別高溫氣冷堆中被廣泛使用。作為第四代候選堆型之一,高溫氣冷堆主要包括球床堆和柱狀堆兩種堆型。在兩種堆型中,石墨主要用作慢化劑、燃料元件基體材料及堆內結構材料。在反應堆運行中,中子輻照使得石墨的相關性能下降甚至可能失效。原材料及成型方式對于石墨的結構、性能及其在輻照中的表現(xiàn)起到?jīng)Q定性的作用。輻照中石墨微觀結構及尺寸的變化是其宏觀熱力學性能變化的內在原因,輻照溫度及劑量對于石墨的結構及性能變化起決定性作用。本文介紹了高溫氣冷堆中核石墨的性能要求及核石墨的生產(chǎn)流程,闡述了不同溫度及輻照條件下石墨熱力學性能及微觀結構的變化規(guī)律,并對當前國內外核石墨的研究現(xiàn)狀及未來核石墨的長期發(fā)展如焦炭的穩(wěn)定供應和石墨的回收進行討論。本文可為有志于研發(fā)用于未來我國商業(yè)化的高溫氣冷堆中的核石墨的生產(chǎn)廠家提供參考。
[Abstract]:Since its first use in CP-1 reactor in 1942, nuclear graphite has been widely used in special high temperature gas cooled reactor because of its excellent comprehensive performance. High temperature gas cooled reactor mainly consists of ball bed reactor and columnar reactor. In the two types of reactor, graphite is mainly used as moderator, base material of fuel element and structural material inside reactor. Neutron irradiation makes the properties of graphite decrease or even fail. The raw material and the forming method for the structure of graphite, The change of microstructure and size of graphite during irradiation is the internal cause of the change of macroscopic thermodynamic properties. Irradiation temperature and dose play a decisive role in the change of structure and properties of graphite. This paper introduces the performance requirements of nuclear graphite in high temperature gas cooled reactor and the production process of nuclear graphite. The variation of thermodynamic properties and microstructure of graphite at different temperatures and irradiation conditions are described. The present research situation of nuclear graphite at home and abroad and the long-term development of nuclear graphite in the future, such as the stable supply of coke and the recovery of graphite, are discussed. The nuclear graphite manufacturers provide reference.
【作者單位】: 清華大學核能與新能源技術研究院先進核能技術協(xié)同創(chuàng)新中心先進反應堆工程與安全教育部重點實驗室;
【基金】:State Scholarship Foundation of China(201406215002) Chinese National S&T Major Project(ZX06901) Tsinghua University Initiative Scientific Research Program(20121088038)~~
【分類號】:TQ127.11

【相似文獻】

相關期刊論文 前2條

1 徐世江;核石墨設計強度[J];新型碳材料;1994年01期

2 ;[J];;年期

,

本文編號:1612833

資料下載
論文發(fā)表

本文鏈接:http://sikaile.net/kejilunwen/huaxuehuagong/1612833.html


Copyright(c)文論論文網(wǎng)All Rights Reserved | 網(wǎng)站地圖 |

版權申明:資料由用戶6fb06***提供,本站僅收錄摘要或目錄,作者需要刪除請E-mail郵箱bigeng88@qq.com