ML21288A039

From kanterella
Revision as of 13:28, 18 January 2022 by StriderTol (talk | contribs) (StriderTol Bot change)
Jump to navigation Jump to search
September 14, 2021, Summary of Public Workshop on Scale/Melcor Source Term Demonstration Project - Pebble-Bed Molten-Salt-Cooled Reactor
ML21288A039
Person / Time
Site: Arkansas Nuclear, River Bend  Entergy icon.png
Issue date: 10/18/2021
From: Jason Schaperow
NRC/NRR/DANU/UART
To: Michael Orenak
NRC/NRR/DANU/UART
Schaperow J
References
Download: ML21288A039 (3)


Text

October 18, 2021 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 Signed by Schaperow, Jason FROM: Jason Schaperow on 10/18/21 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 SEPTEMBER 14, 2021, PUBLIC WORKSHOP ON SCALE/MELCOR SOURCE TERM DEMONSTRATION PROJECT -

PEBBLE-BED MOLTEN-SALT-COOLED REACTOR On September 14, 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 September 14, 2021, workshop covered the application of SCALE and MELCOR to determining source term for a pebble-bed molten-salt-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 110 participants from the NRC, U.S. nuclear industry, international organizations, and other stakeholder organizations (e.g., Union of Concerned Scientists) attended.

CONTACT: Jason Schaperow, NRR/DANU 301-415-6903

M. Orenak 2 The September 14, 2021 workshop was one part of a series of public workshops for the SCALE/MELCOR non-LWR source term demonstration project. Previously, public workshops for heat pipe reactors and high-temperature gas-cooled reactors were held on June 29, 2021, and July 20, 2021, respectively, and the meeting summaries can be found at Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML21202A380 and ML21236A285, respectively.

The September 14, 2021, workshop notice is available in ADAMS at Accession No. ML21155A227, the workshop presentation is available at ADAMS Accession No. ML21256A231, 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.

M. Orenak 3

SUBJECT:

SUMMARY

OF SEPTEMBER 14, 2021, PUBLIC WORKSHOP ON SCALE/MELCOR SOURCE TERM DEMONSTRATION PROJECT -

PEBBLE-BED MOLTEN-SALT-COOLED REACTOR DATE: OCTOBER 18, 2021 DISTRIBUTION:

PUBLIC RidsNrrDanu Resource RidsNrrDanuUarp Resource ADAMS ACCESSION No.: ML21288A039 Office NRR/DANU NRR/DANU NRR/DANU Name JSchaperow MOrenak JSchaperow Date 10/15 /2021 10/15 /2021 10/18 /2021 OFFICIAL RECORD COPY