Published July 1, 2019 | Version v1
Report

Molten Salt Reactor Initiating Event and Licensing Basis Event Workshop Summary

  • 1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Description

Oak Ridge National Laboratory (ORNL) hosted a workshop on identifying potential initiating events for radioactive releases as precursors to licensing basis events for a generic liquid-fuel molten salt reactor (MSR). The workshop was held on May 21 and 22, 2019. Participants included representatives from seven prospective reactor vendors, industry bodies, US and Canadian regulators, US and Canadian national laboratories, and the academic community. Accident sequence evaluation is central to deterministic and risk-informed performance-based reactor safety evaluation processes, and initiating events begin the accident sequence evaluation process. The workshop focused on how MSR initiating events feed into the risk-informed, performance-based reactor safety evaluation process described in DG-1353. This report describes the workshop activities and results, provides a generic list of initiating events involving selected systems, and presents the estimation of the relative frequency and consequences of accident sequences for a few important, high-level initiating events.

Availability note (English)

Available from https://www.osti.gov/servlets/purl/1561637; https://www.osti.gov/biblio/1561637; DOE Accepted Manuscript full text, or the publishers Best Available Version will be available free of charge after the embargo period

Additional details

Publishing Information

Imprint Pagination
24 p.
Report number
ORNL-TM--2019/1246

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
54044343
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
ACCIDENTS; HAZARDS; LICENSING; LIQUID FUELS; MOLTEN SALT REACTORS; PERFORMANCE; REACTIVITY; REACTOR SAFETY; SAFETY ANALYSIS
Descriptors DEC
FUELS; REACTORS; SAFETY

Optional Information

Contract/Grant/Project number
AC05-00OR22725
Funding organization
USDOE (United States)
Secondary number(s)
OSTIID--1561637