Fuel Cycle Modeling and Simulation of the Molten Salt Breeder Reactor
Conference
·
OSTI ID:1410935
- US Naval Academy, Annapolis, MD (United States)
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
The purpose of this work is to perform a neutronic and fuel cycle analysis of the single-fluid Oak Ridge National Laboratory (ORNL) Molten Salt Breeder Reactor (MSBR) as described in ORNL-4541 [1]. Expected design requirements and system outputs were published in this referenced report; the work described herein is focused on building a model of the core, determining the best strategy for modeling the reactor core, and ultimately implementing this modeling/analysis strategy for future research in liquid fueled reactors. Similar analyses for the MSBR using unit cell and full-core models performed using MCNP [2] showed that multiregion models can accurately represent the spectral properties of the multizone MSBR [3,4].
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1410935
- Country of Publication:
- United States
- Language:
- English
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