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首页> 外文会议>Safety Related Issues of Spent Nuclear Fuel Storage; NATO Security Through Science Series C: Environmental Security >SPENT FUEL MANAGEMENT IN POLAND
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SPENT FUEL MANAGEMENT IN POLAND

机译：波兰的燃油管理

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Spent nuclear fuel in Poland is from the two research reactors EWA and MARIA. Information on these reactors and their spent fuel are presented. After discharge, storage has been under water in away-from-reactor (AFR) facilities for EWA spent fuel, and in the reactor pool for MARIA spent fuel. Design information and experience are given for these facilities. rnBecause of lengthy wet storage, a broad programme of physical investigation of the spent fuel and storage facilities condition was begun. Visual inspection showed onset of corrosion after 20 years and strong corrosion after 30 years. Corrosion seems to depend on the presence of fuel under the cladding.rnSipping tests were performed on WWR-SM assemblies for storage times of 4-31 years and a limit for wet storage established. Based on this work, the daily leakage rate of Cs-137 from WWR-SM and WWR-M2 spent fuel was estimated and compared with measurements in 1999 and 2000. The results of systematic sipping test of Ek-10 fuel and WWR-SM fuel assemblies discharged from EWA reactor before 1970 is also described. Additionally, an ultrasonic scanning technique was used to determine the extent of corrosion on cladding surfaces. The equipment for these techniques is described.rnThe condition of the steel liner and aluminium tank of the storage pool was investigated with a wide range of techniques, e.g., dye penetrants, ultrasonic probes, and others. Improvements were made on the basis of results.rnBecause of the limited time for safe wet storage, the concept of dry storage was proposed and is presented in this paper. The spent fuel for dry storage will be encapsulated in stainless steel capsules filled with inert helium. The technology for encapsulating MR spent fuel is described. A similar technique for encapsulating Ek-10 and WWR spent fuels is in the design stage.
机译：波兰用过的核燃料来自两个研究堆EWA和MARIA。介绍了有关这些反应堆及其乏燃料的信息。排放后，已存放在水下的反应堆远离设施（AFR）中，以存放EWA乏燃料，并存放在反应堆池中以存放MARIA乏燃料。这些设施提供了设计信息和经验。 rn由于长期湿存储，开始了对乏燃料和存储设施状况进行广泛物理检查的计划。目视检查显示20年后开始腐蚀，30年后开始强烈腐蚀。腐蚀似乎取决于包层下燃料的存在。rn对WWR-SM组件进行了吸液测试，存储时间为4-31年，并确定了湿存储的极限。基于这项工作，估算了WWR-SM和WWR-M2乏燃料中Cs-137的日漏率，并将其与1999年和2000年的测量结果进行了比较。Ek-10燃料和WWR-SM燃料的系统吸气测试结果还描述了从1970年前从EWA反应堆排放的组件。另外，使用超声波扫描技术来确定包层表面的腐蚀程度。描述了用于这些技术的设备。使用多种技术，例如染料渗透剂，超声探头等，研究了存储池的钢衬和铝罐的状况。在结果的基础上进行了改进。由于安全湿存储的时间有限，提出了干存储的概念，并在本文中进行了介绍。干储存的乏燃料将被封装在装有惰性氦气的不锈钢容器中。描述了用于封装MR乏燃料的技术。在设计阶段，用于封装Ek-10和WWR乏燃料的类似技术。

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