{"title":"Zr-2.5 wt pct Nb核反应堆压力管在300℃高压锂化水中(pH 12.3)的腐蚀/氢化行为","authors":"N. Zreiba, D. Northwood","doi":"10.1007/BF02833557","DOIUrl":null,"url":null,"abstract":"","PeriodicalId":276653,"journal":{"name":"Journal of Materials for Energy Systems","volume":"146 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"1985-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"1","resultStr":"{\"title\":\"The corrosion/hydriding behavior of Zr-2.5 wt pct Nb nuclear reactor pressure tubing in pressurized Lithiated Water (pH 12.3) at 300 °C\",\"authors\":\"N. Zreiba, D. Northwood\",\"doi\":\"10.1007/BF02833557\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"\",\"PeriodicalId\":276653,\"journal\":{\"name\":\"Journal of Materials for Energy Systems\",\"volume\":\"146 1\",\"pages\":\"0\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"1985-09-01\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"1\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Journal of Materials for Energy Systems\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://doi.org/10.1007/BF02833557\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Materials for Energy Systems","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1007/BF02833557","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}