Purpose
NRC is sponsoring public workshops on the SCALE/MELCOR non-LWR Fuel Cycle Demonstration Project. The workshops are part of the agency’s efforts to prepare for safety reviews of non-LWR license applications. On July 11, 2024, from 1 – 3 P.M., the NRC will host a workshop highlighting the molten salt reactor (MSR) nuclear fuel cycle. This workshop will be held via MS Teams and the following topics will be covered:
• An overview of a representative fuel cycle that covers enrichment and transportation of uranium hexafluoride (UF6), fresh fuel manufacturing, spent fuel transportation and storage;
• SCALE methods for predicting criticality, spent fuel fission product inventory and decay heats, as well as sample SCALE results; and,
• MELCOR methods and sample results for accident progression and fission product release to the environment.
• An overview of a representative fuel cycle that covers enrichment and transportation of uranium hexafluoride (UF6), fresh fuel manufacturing, spent fuel transportation and storage;
• SCALE methods for predicting criticality, spent fuel fission product inventory and decay heats, as well as sample SCALE results; and,
• MELCOR methods and sample results for accident progression and fission product release to the environment.
Meeting Feedback
Meeting Dates and Times
07/11/24, 1PM - 3PM EDT
Meeting Location
Teleconference
Webinar
Webinar Meeting Number: N/A
Webinar Password: N/A
Contact
Lucas Kyriazidis
(301) 415-7834
Shawn Campbell
(301) 415-0244
Participation Level
Information with Q&A
NRC Participants
NRC Staff
External Participants
Oak Ridge National Lab
Industry Representatives
Sandia National Lab
Teleconference
Bridge Number: 3015762978
Conference ID: 842983115
Bridgeline: 301-576-2978
Conference ID: 842 983 115#
For additional details, please call the NRC meeting contact listed on the NRC Public Meeting Schedule or call the NRC’s toll-free number, 1-800-368-5642, and ask the operator to be connected to the meeting contact Lucas Kyriazidis.