ML21236A285

From kanterella
Revision as of 01:35, 23 November 2024 by StriderTol (talk | contribs) (StriderTol Bot change)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
July 20, 2021, Summary of Public Workshop on Scale/Melcor Source Term Demonstration Project - High-Temperature Gas-Cooled Reactor
ML21236A285
Person / Time
Issue date: 08/31/2021
From: Jason Schaperow
NRC/NRR/DANU
To: Michael Orenak
NRC/NRR/DANU
Schaperow J
References
Download: ML21236A285 (2)


Text

MEMORANDUM TO: Michael Orenak, Chief Advanced Reactor Technical Branch 1 Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation FROM: Jason Schaperow, Senior Reactor Systems Engineer Advanced Reactor Technical Branch 1 Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation

SUBJECT:

SUMMARY

OF JULY 20, 2021, PUBLIC WORKSHOP ON SCALE/MELCOR SOURCE TERM DEMONSTRATION PROJECT - HIGH-TEMPERATURE GAS-COOLED REACTOR On July 20, 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 July 20, 2021, workshop covered the application of SCALE and MELCOR to determining source term for a high-temperature gas-cooled 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 140 participants from the NRC, U.S. nuclear industry, international organizations, and other stakeholder organizations (e.g., Union of Concerned Scientists) attended.

The July 20, 2021 workshop was one part of a series of public workshops for the SCALE/MELCOR non-LWR source term demonstration project. Previously, a public workshop for heat-pipe reactors was held on June 29, 2021 and the meeting summary can be found at CONTACT: Jason Schaperow, NRR/DANU 301-415-6903 August 31, 2021 Signed by Schaperow, Jason on 08/31/21

Agencywide Documents Access and Management System (ADAMS) at Accession No. ML21202A380. The remaining public workshop in the series will be on molten salt cooled reactors and is planned for September 14, 2021.

The July 20, 2021, workshop notice is available in ADAMS at Accession No. ML21155A217, the workshop presentation is available at ADAMS Accession No. ML21200A179, 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.