ML21202A380
| ML21202A380 | |
| Person / Time | |
|---|---|
| Issue date: | 07/28/2021 |
| From: | Jason Schaperow NRC/NRR/DANU/UART |
| To: | Michael Orenak NRC/NRR/DANU/UART |
| Schaperow J | |
| References | |
| Download: ML21202A380 (2) | |
Text
July 23, 2021 MEMORANDUM TO: Michael Orenak, Chief Advanced Reactor Technical Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation FROM: Jason Schaperow, Senior Reactor Systems Engineer /RA/
Advanced Reactor Technical Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF JUNE 29, 2021, PUBLIC WORKSHOP ON SCALE/MELCOR SOURCE TERM DEMONSTRATION PROJECT - HEAT PIPE REACTOR On June 29, 2021, the U.S. Nuclear Regulatory Commission (NRC) staff conducted a public workshop on the SCALE/MELCOR non-LWR source term demonstration project. The project is part of the agencys efforts to prepare for safety reviews of non-LWR license applications. The project objectives are as follows:
- Understand severe accident behavior in non-LWRs,
- Provide insights for developing regulatory guidance,
- Develop publicly available input models for representative designs, and
- Facilitate dialogue on the staffs approach for determining source term.
The June 29, 2021, workshop covered the application of SCALE and MELCOR to determining source term for a heat pipe reactor. During the workshop, NRC, Sandia National Laboratories, and Oak Ridge National Laboratory staff presented SCALE and MELCOR modeling methods and results for simulating core fission product inventory and decay heat during normal operation and core heat up and fission product release to the environment during an accident. A total of 170 participants from the NRC, U.S. nuclear industry, international organizations, and other stakeholder organizations (e.g., Union of Concerned Scientists) attended. Additional public workshops are planned for high temperature gas cooled reactors and molten salt cooled reactors on July 20 and September 14, respectively.
The workshop notice is available in the NRCs Agencywide Documents Access and Management System (ADAMS) at Accession No. ML21144A278, the workshop presentation is available at ADAMS Accession No. ML21179C060, and a video recording of the workshop is available here. This workshop summary does not include an attendee list, because of the large number of attendees.
ML21202A380 NRC-001 OFFICE NRR/DANU/UART/SE NRR/DANU/UART/BC NRR/DANU/UART/SE NAME JSchaperow MOrenak JSchaperow DATE 07/22/2021 07/22/2021 07/23/2021