Molten Salt Reactor Initiating Event and Licensing Basis Event Workshop Summary

Holcomb, David Eugene; Huning, Alex; Yigitoglu, Askin Guler; Muhlheim, Michael David; Poore, Willis; Flanagan, G.F.

doi:10.2172/1561637

Cited by 4 publications

(5 citation statements)

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“…Recently, ORNL hosted a workshop with the goal of identifying initiating events (IE) for radioactive releases as precursors to licensing basis events (LBE) for salt-fueled MSRs [57]. They noted 140 different IEs that warranted further investigation.…”

Section: Salt-fueled Molten Salt Reactorsmentioning

confidence: 99%

Functional Requirements for the Modeling and Simulation of Advanced (Non-LWR) Reactor Mechanistic Source Term

Shahbazi

Grabaskas

2020

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Section: Salt-fueled Molten Salt Reactorsmentioning

confidence: 99%

Functional Requirements for the Modeling and Simulation of Advanced (Non-LWR) Reactor Mechanistic Source Term

Shahbazi

Grabaskas

2020

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“…In 2019, ORNL held a workshop for MSR design and research organizations to identify the potential licensing basis events: anticipated operational occurrences (AOOs), design basis events (DBEs), and beyond design basis events (BDBEs) [64]. In many cases, the issues identified in the workshop can be resolved by the design teams using state-of-the-art, adequately validated calculational tools.…”

Section: Licensing Basis Events (Lbes)mentioning

confidence: 99%

Molten Salt Reactor Fundamental Safety Function PIRT

Holcomb

Huning

Muhlheim

et al. 2021

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The phenomenon identification and ranking table (PIRT) process was employed to evaluate the current capability to assess the ability of liquid-salt-fueled molten salt reactors to achieve their fundamental safety functions (FSFs). The PIRT process provides a structured mechanism to elicit and document expert opinions on the most important phenomena and the corresponding level of knowledge with regard to achieving the FSFs. The PIRT panel included reactor developers, accident progression evaluation tool developers, US Department of Energy (DOE) national laboratory technical staff, university researchers, and US Nuclear Regulatory Commission (NRC) staff. The information-gathering process concentrated on phenomena related to accidents in which the fuel salt-including any in the cover gas-has been released from the first barrier layer. This information-gathering process included identifying all potential accidents that could result in the release of a substantial amount of radionuclides that could breach or bypass the first barrier. The PIRT did not identify any previously unrecognized systemic vulnerabilities. However, the elicitation process identified several areas with low levels of knowledge and significant potential impact on accident progression. These areas either require additional research to improve the state of knowledge or additional design conservatism to accommodate the remaining unknowns.

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“…Of the identified LBEs, breaches of the primary fuel salt piping and drain tank would result in the release of radionuclides into the reactor containment cell and represent LBEs that are qualitatively estimated to be DBEs and BDBEs, respectively [126]. The conditions at the time of a breach are important as unique conditions-such as reactor containment cell open or not properly inertedcould result in high consequences.…”

Section: Licensing Basis Eventsmentioning

confidence: 99%

“…), could result in an event of varying severity and consequence dependent on the size and location of the breach. Although event frequency is dependent on the MSR design (loop, integral/pool type, modular), the consensus among the ORNL MSR LBE workshop participants is that this LBE can probably be classified as a design DBE or lower [126]. For many MSR designs and most locations of potential boundary breaches, the salt will release into a reactor containment cell designed with this scenario in mind.…”

Section: Salt Releasementioning

confidence: 99%