1. American National Standard for Neutron and Gamma-Ray Fluence-to-Dose Factors;American Nuclear Society Standards Committee Working Group ANS-6.1.1-1991,1991
2. Calculating the effective delayed neutron fraction in the molten salt fast reactor: Analytical, deterministic and Monte Carlo approaches;Aufiero;Ann. Nucl. Energy,2014
3. Bae, J.W., Betzler, B.R., Wieselquist, W.A., 2021. Solving Advection Problems with Isotopic Evolution with SCALE/ORIGEN. In: The International Conference on Mathematics and Computational Methods Applied To Nuclear Science and Engineering. Raleigh, North Carolina, USA.
4. Betzler, B.R., Bekar, K.B., Wieselquist, W.A., Hart, S.W., Stimpson, S.G., 2019a. Molten Salt Reactor Fuel Depletion Tools in SCALE. In: Global Top Fuel. Seattle, Washington, USA.
5. Molten Salt Reactor Campaign Modeling and Simulation Program Plan;Betzler,2018