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Title: Molten Salt Reactor Fuel Depletion Tools in SCALE

Abstract

Molten salt reactor depletion modeling and simulation tools have been implemented into the SCALE suite for reactor analysis and design developed by Oak Ridge National Laboratory. For depletion with material feeds and removals, additional removal and feed rate functionalities are being developed in ORIGEN to account for these flows during depletion. To track separate fuel and waste materials, additional functions and an iterative scheme are being added to the SCALE/TRITON lattice physics tool. The functionality of these tools has been demonstrated in part for previous analyses using external scripts that manage SCALE/TRITON calculations. Direct implementation of these functionalities into SCALE provides for a more ecient, more accurate material accountability methodology that is accessible to external SCALE users with a new input definition. These implementations are being tested for accuracy and to demonstrate their applicability to predefined molten salt reactor use case problems. This work demonstrates the capability of the SCALE modeling and simulation tools for reactor physics and fuel cycle analysis of molten salt reactor concepts.


Citation Formats

Betzler, Benjamin R., Bekar, Kursat B., Wieselquist, William, Hart, Shane W., and Stimpson, Shane G. Molten Salt Reactor Fuel Depletion Tools in SCALE. United States: N. p., 2019. Web.
Betzler, Benjamin R., Bekar, Kursat B., Wieselquist, William, Hart, Shane W., & Stimpson, Shane G. Molten Salt Reactor Fuel Depletion Tools in SCALE. United States.
Betzler, Benjamin R., Bekar, Kursat B., Wieselquist, William, Hart, Shane W., and Stimpson, Shane G. Sun . "Molten Salt Reactor Fuel Depletion Tools in SCALE". United States. https://www.osti.gov/servlets/purl/1566988.
@article{osti_1566988,
title = {Molten Salt Reactor Fuel Depletion Tools in SCALE},
author = {Betzler, Benjamin R. and Bekar, Kursat B. and Wieselquist, William and Hart, Shane W. and Stimpson, Shane G.},
abstractNote = {Molten salt reactor depletion modeling and simulation tools have been implemented into the SCALE suite for reactor analysis and design developed by Oak Ridge National Laboratory. For depletion with material feeds and removals, additional removal and feed rate functionalities are being developed in ORIGEN to account for these flows during depletion. To track separate fuel and waste materials, additional functions and an iterative scheme are being added to the SCALE/TRITON lattice physics tool. The functionality of these tools has been demonstrated in part for previous analyses using external scripts that manage SCALE/TRITON calculations. Direct implementation of these functionalities into SCALE provides for a more ecient, more accurate material accountability methodology that is accessible to external SCALE users with a new input definition. These implementations are being tested for accuracy and to demonstrate their applicability to predefined molten salt reactor use case problems. This work demonstrates the capability of the SCALE modeling and simulation tools for reactor physics and fuel cycle analysis of molten salt reactor concepts.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2019},
month = {9}
}

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