POD Evaluation of NDE Techniques for Canister-Components for Risk Assessment of Nuclear Waste Encapsulation

نویسندگان

  • C. Müller
  • M. Pavlovic
  • K. Takahashi
  • U. Ewert
  • M. Rosenthal
  • G. Brekow
  • R. Böhm
چکیده

In order to handle long living radioactive waste Sweden is planning to build a deep repository that requires no monitoring by future generations. The spent nuclear fuel will be encapsulated in copper canisters consisting of a graphite cast iron insert shielded by an outer 30-50 mm thick copper cylinder for corrosion protection. A subpart of the final risk assessment is to determine the risk of premature canister leak caused by defects in the sealing weld and the enveloping components. Therefore the quality of the production process and the reliability of the NDT system must be satisfactorily determined and combined to derive assumptions regarding the frequency of undetected welding defects for the ensemble of canisters. The reliability of the NDT systems can be derived from POD curves which are investigated for X-ray and mainly for ultrasonic techniques applied by SKB. These complex canister are not only a challenge for the NDT techniques but also for the reliability investigation requiring a further development of the common “â versus a” approach due to the complex multidimensional situation and risk assessment. The reliability study started in 2003 for the welds and was in 2006 extended to the iron cast insert and the copper shield. The evaluation technique is developed in applying a multi parameter and data field-POD.

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

ثبت نام

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

منابع مشابه

Ultrasonic Investigations on Copper Canister Welds in Preparation for the Storage of Spent Nuclear Fuel in a Deep Repository

Abstract. The Swedish KBS-3 design for the disposal of spent fuel is based on its encapsulation cast iron cylinders that have an outer 30 – 50 mm thick shield of copper and deposition in crystalline rock embedded in bentonite at a depth of about 500 m. The KBS-3 system is based on a multi barrier system where the canister is the primary barrier. The cast iron insert gives the canister the neces...

متن کامل

Afrl-rx-wp-ja-2016-0304 Best Practices for Evaluating the Capability of Nondestructive Evaluation (nde) and Structural Health Monitoring (shm) Techniques for Damage Characterization (postprint)

A comprehensive approach to NDE and SHM characterization error (CE) evaluation is presented that follows the framework of the ‘ahat-versus-a’ regression analysis for POD assessment. Characterization capability evaluation is typically more complex with respect to current POD evaluations and thus requires engineering and statistical expertise in the model-building process to ensure all key effect...

متن کامل

Historical relationship between performance assessment for radioactive waste disposal and other types of risk assessment.

This article describes the evolution of the process for assessing the hazards of a geologic disposal system for radioactive waste and, similarly, nuclear power reactors, and the relationship of this process with other assessments of risk, particularly assessments of hazards from manufactured carcinogenic chemicals during use and disposal. This perspective reviews the common history of scientifi...

متن کامل

Advances in Ultrasonic Instrumentation for Non-Destructive Evaluation of Mechanical Components of Nuclear Reactors

In the first and second stage nuclear program of Department of Atomic Energy (DAE), technologies are matured for Pressurised Heavy Water Reactors (PHWRs) and Sodium-Cooled Fast Breeder Reactors (FBRs). Pre-service-Inspection (PSI), In-Service-Inspection (ISI) and Post-Irradiation-Examination (PIE) procedures are carried out for mechanical components and structures/assemblies of these reactors, ...

متن کامل

Advances in Ultrasonic Instrumentation for Non-Destructive Evaluation of Mechanical Components of Nuclear Reactors

In the first and second stage nuclear program of Department of Atomic Energy (DAE), technologies are matured for Pressurised Heavy Water Reactors (PHWRs) and Sodium-Cooled Fast Breeder Reactors (FBRs). Pre-service-Inspection (PSI), In-Service-Inspection (ISI) and Post-Irradiation-Examination (PIE) procedures are carried out for mechanical components and structures/assemblies of these reactors, ...

متن کامل

ذخیره در منابع من


  با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

ثبت نام

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

عنوان ژورنال:

دوره   شماره 

صفحات  -

تاریخ انتشار 2007