HPS 66th Annual Meeting

Phoenix, Arizona
July 25th-29th 2021

Single Session



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TAM-A - AAHP Special Session - Nuclear Site Decommissioning

North 221ABC   08:00 - 12:00

 
TAM-A.1   08:00  Decommissioning Challenges at the Molten-Salt Reactor Experiment Site E Ablequist*, UCOR ; T Morgan

Abstract: This discussion will focus on the MSRE site decommissioning status and unique challenges faced during this project in Oakridge, TN.

TAM-A.2   08:45  Decommissioning of the Nuclear Ship Savannah E Koehler*, Maritime Administration

Abstract: The Nuclear Ship Savannah was designed and built in late 1950’s as part of the Atoms for Peace initiative. The first of its kind ship sailed the world for more then 10 years demonstrating the safe and peaceful use of nuclear technology. The ship is in the process of being decommissioned and the challenges of ensuring radiological controls, maintaining a floating ship integrity and protecting this National Historic Landmark require unique and innovative solutions described in this presentation.

09:30  BREAK

TAM-A.3   10:00  Measurement and Control of Special Nuclear Material During D&D of the MSRE and K-25 J Chapman*, NNSA

Abstract: Tens of thousands of Nondestructive Assay (NDA) measurements of special nuclear material (SNM) were conducted from the late 1980s through 2015 at the K-25 Gaseous Diffusion Plant (GDP). Other radioisotopes were also measured to establish proper health and safety controls to personnel, involved in the massive dismantlement and decommissioning effort, that began in earnest, in 2008, and completed last year. Meanwhile, before, during and after defueling of the Molten Salt Reactor Experiment in the 1990s, hundreds of measurements were conducted to manage the SNM and to protect personnel from exposure to U-233 and U-232. This paper will present the measurement and control NDA methods used for material control and accountability and criticality safety for MSRE and K-25, as performed directly or as assessed by the author over a 25-year period. Additional discussion, related to these measurement programs will be pursued: 1) DNFSB recommendation 2007-1, “Safety-Related In Situ Nondestructive Assay of Radioactive Materials,” and 2) the development of ANSI ANS8.28, “Administrative Practices for the Use of Nondestructive Assay Measurements for Nuclear Criticality Safety.”

TAM-A.4   10:45  Nuclear Energy Institute Regulatory Update M Phalen*, NEI

Abstract: This discussion will discuss the Nuclear Energy Institutes’ (NEI’s) role in decommissioning of nuclear power facilities as well as some of the key regulatory changes ongoing in the industry.

TAM-A.5   11:30  Advanced Radiological Characterization at Nuclear Decommissioning Sites N Rashidifard*, RSCS

Abstract: There are several nuclear facilities that need to characterize radiological areas where entry by workers is either prohibitive or very high risk. The integration of advanced characterization tools, robotic platforms and powerful Building Information 3D Models can perform characterization with highly scalable and innovative planning and work execution capabilities. All of this can be accomplished without workers entering the spaces.



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