A preliminary neutronic evaluation of the high temperature nuclear reactor (HTTR) using reprocessed fuel

Author:

Sousa R.V.,Tanure L.P.A.R.,Costa D.F.,Pereira C.,Veloso M.A.F.,de Oliveira A.H.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference22 articles.

1. Argonne National Laboratory, 2004. Lab-Scale Demonstration of the UREX+ Process. WM’04 Conference, Tucson, AZ. USA, February 29–March 4 (2004).

2. Fast accelerator driven subcritical system for energy production using burned fuel;Barros;Fusion Science and Technology,2012

3. Study of an ADS loaded with thorium and reprocessed fuel;Barros;Science and Technology of Nuclear Installations,2012

4. Bess, J.D., Fujimoto, N., Dolphin, B.H., Snoj, L., Zukeran, A., 2009. Evaluation of the Start-Up Core Physics Tests at Japan’s High Temperature Engineering Test Reactor (Fully-Loaded Core). INL/EXT-08-14767. Idaho National Laboratory, USA.

5. Neutronic evaluation of the non-proliferating reprocessed nuclear fuels in pressurized water reactors;Cota;Annals of Nuclear Energy,1997

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