Depletion analysis on long-term operation of the conceptual Molten Salt Actinide Recycler & Transmuter (MOSART) by using a special sequence based on SCALE6/TRITON

Author:

Sheu R.J.,Chang C.H.,Chao C.C.,Liu Y.-W.H.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference17 articles.

1. DeHart, M.D., 2009. TRITON: A Two Dimensional Transport and Depletion Module for Characterization of Spent Nuclear Fuel. ORNL/TM-2005/39, Version 6, vol. I, Sect. T1. Oak Ridge National Laboratory, Oak Ridge, TN, USA.

2. Forsberg, C.W., 2007. Thermal- and fast-spectrum molten salt reactors for actinide burning and fuel production. In: Proceeding of Global 2007, Boise, Idaho, USA.

3. Isotopic depletion and decay methods and analysis capabilities in SCALE;Gauld;Nucl. Technol.,2011

4. Gen-IV, 2010. The Generation IV International Forum. .

5. ICRP, 1996. Publication 72, Annals of the ICRP 26. Pergamon Press.

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