首页> 外文会议>American Ceramic Society >TEM INVESTIGATION OF A CERAMIC WASTE FORM FOR IMMOBILIZATION OF PROCESS SALTS GENERATED DURING ELECTROMETALLURGICAL TREATMENT OF SPENT NUCLEAR FUEL

【24h】

TEM INVESTIGATION OF A CERAMIC WASTE FORM FOR IMMOBILIZATION OF PROCESS SALTS GENERATED DURING ELECTROMETALLURGICAL TREATMENT OF SPENT NUCLEAR FUEL

机译：陶瓷废料形式对核燃料电气冶金治疗过程中加工盐固定化的TEM调查

获取原文

页面导航

摘要
著录项
相似文献
相关主题

摘要

Transmission electron microscopy (TEM) examination is presented of the microstructure of a ceramic waste form developed at Argonne National Lab -West for imobilization of actinides and fission products present in an electrorefiner salt. The material is produced by occluding the salt in zeolite granules, followed by hot isostatic pressing of the occluded zeolite in a mixture with a borosilicate glass. The paper presents results from a cold surrogate ceramic waste form, as well as ~(239)Pu and ~(238)Pu loaded samples.

机译：透射电子显微镜（TEM）检查提出了在Argonne National Lab -west的陶瓷废物形式的微观结构，用于灌注电火虫盐中存在的散曲线和裂变产物。通过在沸石颗粒中封闭盐来制备材料，然后在用硼硅酸盐玻璃中的混合物中热等静脉压制闭塞沸石。本文提出了冷替代陶瓷废物形式的结果，以及〜（239）PU和〜（238）PU加载样品。

著录项

来源
《American Ceramic Society》|2000年||共8页
会议地点
作者
Wharton Sinkler; David W. Esh; Thomas P. OHolleran;
展开▼
作者单位

展开▼
会议组织
原文格式 PDF
正文语种
中图分类 TQ17-532;
关键词

相似文献

外文文献
中文文献
专利

1. A DESCRIPTION OF THE CERAMIC WASTE FORM PRODUCTION PROCESS FROM THE DEMONSTRATION PHASE OF THE ELECTROMETALLURGICAL TREATMENT OF EBR-II SPENT FUEL [J] . MICHAEL F. SIMPSON, K. MICHAEL GOFF, STEPHEN G. JOHNSON Nuclear Technology . 2001,第3期

机译：电化学法处理EBR-II燃油的示范阶段对陶瓷废物形态生产过程的描述
2. Murataite: a matrix for immobilizing waste generated in radiochemical reprocessing of spent nuclear fuel [J] . Lizin Andrey A., Tomilin Sergey V., Poglyad Sergey S., Journal of Radioanalytical and Nuclear Chemistry: An International Journal Dealing with All Aspects and Applications of Nuclear Chemistry . 2018,第3期

机译：Murataite：一种用于固定废化核燃料的放射性化再加工中产生的废物的基质
3. Sodium aluminum-iron phosphate glass-ceramics for immobilization of lanthanide oxide wastes from pyrochemical reprocessing of spent nuclear fuel [J] . Stefanovsky S. V., Stefanovsky O. I., Kadyko M. I., Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2018,第期

机译：铝 - 铁铝 - 铁玻璃 - 用于固定镧系元素氧化镧氧化物废弃物的废核燃料
4. TEM INVESTIGATION OF A CERAMIC WASTE FORM FOR IMMOBILIZATION OF PROCESS SALTS GENERATED DURING ELECTROMETALLURGICAL TREATMENT OF SPENT NUCLEAR FUEL [C] . Wharton Sinkler, David W. Esh, Thomas P. OHolleran American Ceramic Society . 2000

机译：陶瓷废料形式对核燃料电气冶金治疗过程中加工盐固定化的TEM调查
5. The durability of single, dual, and multiphase titanate ceramic waste forms for nuclear waste immobilization [D] . Harkins, Devin J. H. 2016

机译：核废物固定化的单一，双和多相型钛酸盐陶瓷废物形式的耐久性
6. Ceramic Mineral Waste-Forms for Nuclear Waste Immobilization [O] . Albina I. Orlova, Michael I. Ojovan 2019

机译：用于固定核废料的陶瓷矿物废料形式
7. A finite difference model used to predict the consolidation of a ceramic waste form produced from the electrometallurgical treatment of spent nuclear fuel. [O] . Bateman, K. J., Capson, D. D. 2004

机译：一种有限差分模型，用于预测废核燃料的电冶金处理产生的陶瓷废料的固结。
8. TEM investigation of a ceramic waste form for immobilization of process salts211 generated during electrometallurgical treatment of spent nuclear fuel [R] . Esh, D. W., Frank, S. M., Goff, K. M., 1999

机译：用于固定在废核燃料的电冶金处理期间产生的工艺盐211的陶瓷废物形式的TEm研究

TEM INVESTIGATION OF A CERAMIC WASTE FORM FOR IMMOBILIZATION OF PROCESS SALTS GENERATED DURING ELECTROMETALLURGICAL TREATMENT OF SPENT NUCLEAR FUEL

摘要

著录项

相似文献

相关主题

期刊订阅