Preliminary design evaluation of a natural circulation molten salt irradiation loop

Sandesh Bhaskar, Abdalla Abou-Jaoude

Research output: Contribution to journalConference articlepeer-review

2 Scopus citations

Abstract

Many promising Molten Salt Reactor (MSR) concepts under development rely on relatively untested salt compositions. Irradiation data will likely be necessary for the licensing of these concepts. A feasibility study is currently underway at Idaho National Laboratory to establish the possibility of hosting a compact molten salt irradiation loop inside the Advanced Test Reactor (ATR). A case study for a uranium-fueled chloride-based salt is examined in this paper. Thermal hydraulic simulations are conducted using the system code, SAM, to scope the achievable natural circulating velocities and inform design decisions.

Original languageEnglish
Pages (from-to)1895-1896
Number of pages2
JournalTransactions of the American Nuclear Society
Volume121
Early online dateNov 2019
DOIs
StatePublished - Nov 2019
Event2019 Transactions of the American Nuclear Society, ANS 2019 - Washington, United States
Duration: Nov 17 2019Nov 21 2019

Fingerprint

Dive into the research topics of 'Preliminary design evaluation of a natural circulation molten salt irradiation loop'. Together they form a unique fingerprint.

Cite this