首页> 外文OA文献 >MCO Pressurization analysis of spent nuclear fuel transporation and storage

【2h】

MCO Pressurization analysis of spent nuclear fuel transporation and storage

机译：废核燃料运输和储存的mCO增压分析

代理获取

本网站仅为用户提供外文OA文献查询和代理获取服务，本网站没有原文。下单后我们将采用程序或人工为您竭诚获取高质量的原文，但由于OA文献来源多样且变更频繁，仍可能出现获取不到、文献不完整或与标题不符等情况，如果获取不到我们将提供退款服务。请知悉。

页面导航

著录项
引文网络
相似文献
相关主题

著录项

作者
Ogden, D. M.;
展开▼
作者单位

展开▼
年度 1996
总页数
原文格式 PDF
正文语种
中图分类

相似文献

外文文献
中文文献
专利

1. ECONOMIC ANALYSIS ON DIRECT USE OF SPENT PRESSURIZED WATER REACTOR FUEL IN CANDU REACTORS-III: SPENT DUPIC FUEL DISPOSAL COST [J] . WON IL KO, HANGBOK CHOI, GYUHONG ROH Nuclear Technology . 2001,第2期

机译：直接在坎杜反应器中使用加压加压反应器燃料的经济分析-III：双重燃料消耗成本
2. Determining initial enrichment, burnup, and cooling time of pressurized-water-reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden [J] . A. Favalli, D. Vo, B. Grogan, Nuclear Instruments & Methods in Physics Research . 2016,第Juna1期

机译：通过分析在瑞典的Clab临时燃料存储设施中测量的被动伽玛光谱，确定压水反应堆乏燃料组件的初始富集，燃烧和冷却时间
3. Simultaneous Determination of Caesium, Neodymium, Uranium and Plutonium Isotopes in Pressurized Water Reactor Spent Nuclear Fuels by Isotope Dilution Mass Spectrometry [J] . Jung Suk Kim, Young Shin Jeon, Yang-Soon Park Asian Journal of Chemistry: An International Quarterly Research Journal of Chemistry . 2013,第12期

机译：同位素稀释质谱法同时测定压水堆乏核燃料中的铯，钕，铀和P同位素
4. DETERMINATION OF INITIAL ENRICHMENT, BURNUP, AND COOLING TIME OF PRESSURIZED-WATER-REACTOR SPENT FUEL ASSEMBLIES BY ANALYSIS OF PASSIVE GAMMA SPECTRA MEASURED AT THE CLAB INTERIM-FUEL STORAGE FACILITY IN SWEDEN [C] . D. Vo, A. Favalli, B. Grogan, Annual meeting of the Institute of Nuclear Materials Management . 2015

机译：瑞典CLAB中间燃料储存设施被动伽马谱分析法测定加压水反应器燃料组件的初始富集，燃烧和冷却时间。
5. Automated Defect Detection in Spent Nuclear Fuels in Wet Storage Using Machine Learning and Image Analysis Techniques [D] . Brayfindley, Evangelina. 2019

机译：使用机器学习和图像分析技术在湿储存中的废核燃料中自动缺陷检测
6. Pressurized water reactor spent nuclear fuel data library produced with the Serpent2 code [O] . Zsolt Elter, Li Pöder Balkeståhl, Erik Branger, 2020

机译：加压水反应器用Serpent2代码生产的核燃料数据库
7. SPENT NUCLEAR FUEL (SNF) PROJECT CANISTER STORAGE BUILDING (CSB) MULTI CANISTER OVERPACK (MCO) SAMPLING SYSTEM VALIDATION (OCRWM) [O] . Black, D. M., Klem, M. J. 2003

机译：燃料核燃料（sNF）项目储罐建筑（CsB）多罐装过滤（mCO）取样系统验证（OCRWm）
8. MCO Pressurization analysis of spent nuclear fuel transporation and storage [R] . Ogden, D. M. 1996

机译：废核燃料运输和储存的mCO增压分析

MCO Pressurization analysis of spent nuclear fuel transporation and storage

著录项

引文网络

相似文献

相关主题

期刊订阅