WM2026 Conference

Time:  Sunday 0800 – 1700 – breaks and lunch provided

Description: Researchers at Argonne National Laboratory have developed guidance documents on aging management for spent fuel during extended dry storage and subsequent transportation for the U.S. Department of Energy (DOE) and the International Atomic Energy Agency (IAEA). [1-5]. Argonne researchers also pioneered studies of spent fuel canister gas leakage detection [6-9], as well as other environmental aging degradation mechanisms of critical components such as hydride reorientation and embrittlement of high-burnup (HBU) fuel cladding alloys, elastomeric O-ring seals and concrete shields and overpacks. Moreover, Argonne researchers have developed methodology to address extension of intervals for periodic leakage rate testing of Type B radioactive and fissile materials transportation packaging [10-13]. 

In this workshop we will present and discuss key elements of aging management for spent fuel during extended storage and subsequent transportation, including major aging management activities on scoping evaluation of structures, systems and components (SSCs) that are important to safety (ITS), time-limited ageing analyses (TLAAs), ageing management programs (AMPs), including inspection, monitoring, mitigation, repair, and operating experience and lessons learned. We will also illustrate the methodology for extending internals of periodic leakage rate testing for Type B radioactive and fissile material transportation packagings. Emphases in the workshop are on the principles and practices of aging management, drawing examples from applications and industry practices, based on the latest guidance from the regulatory authorities in the U.S. and IAEA. 

The workshop will be led by subject matter experts who have developed and taught the DOE Packaging University Program training courses on (1) ASME Boiler and Pressure Vessel Code for nuclear transport and storage, and (2) QA for transport packaging and storage cask since 2015.

Learning Objectives:

1. Recognize the technical basis for aging management of spent nuclear fuel for extended storage and subsequent transportation
2. Describe TLAAs and AMPs and their main attributes
3. Describe scoping evaluation of SSCs that are ITS; and
4. Identify technologies that can be used for inspection, monitoring, repair and mitigation.

Audience:

The target audience includes US and international professionals attending WM26, who are interested in aging management of spent fuel for existing and future advanced reactors. The methodology of extending periodic leakage rate testing intervals for transportation packaging is also of interest to the targeted audience.

Prerequisites:

There are no prerequisites required relative to the learning topic prior to attendance

Instructors:

Dr. Yung Liu, Dr. Zenghu Han, Dr. Christopher Gastl, and Brian Gutherman