German know-how on Pu recycling and its utilisation for disposition of weapons-grade Pu

被引:0
|
作者
Schlosser, GJ [1 ]
机构
[1] Siemens AG, Power Generat Grp, D-91050 Erlangen, Germany
来源
PROCEEDINGS OF THE WORKSHOP ON THE PHYSICS AND FUEL PERFORMANCE OF REACTOR-BASED PLUTONIUM DISPOSITION | 1999年
关键词
D O I
暂无
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The MOX introduction in LWRs (PWR and BWR) was started in Germany with initial steps of design in the early 70s (Part I). The process of commercial utilisation of Pu recycling was started on the basis of these designs at KWO (PWR at Obrigheim) and KRB-A (BWR at Gundremmingen). The needs of testing and validation of used methods could mainly be fulfilled by the insertion of initial MOX FA reloads. Experiments with these early MOX FAs have been conducted under fully realistic power reactor conditions for neutronic/nuclear and fuel/technological aspects. The validated design procedures and experimental results have been used in the MOX licensing process (Part II) for the other German reactors which started Pu recycling up to now. The licensing requirements are fully in compliance with e.g, licensing for U- and U/Gd FAs at higher enrichment for increased burn-up, The main interest of the presentation (Part ill) is to show the way in which existing know-how can be used to help speed up the disposition of excess weapons grade Pu. The PWR relevant MOX know-how was used in bilateral co-operation between Germany and Russia in the past and is now introduced in the new trilateral co-operation by France, Germany and Russia. Via the consortium led by Siemens Power Corporation the BWR specific MOX know-how can also be utilised in the US programme for reactor based disposition of weapons-grade Pu, Besides physics and fuel performance of MOX the above mentioned projects include the design and construction of MOX fuel fabrication facilities based on industrially proven technology and existing equipment for commercial recycling of reactor grade Pu.
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页码:73 / 83
页数:11
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