Comparative study on various thermal power for gas cooled fast reactor with uranium plutonium nitride fuel

Author:

Syarifah Ratna Dewi,Arkundato Artoto,Rohman Lutfi,Su'ud Zaki

Publisher

AIP Publishing

Reference12 articles.

1. Lamarsh J R Introduction to Nuclear Engineering (Addison-Wesley Publishing Company Inc Massachusetts) pp. 1–2 (1983)

2. GIF (The Generation IV International Forum) and the OECD Nuclear Energy Agency, Technology Roadmap Update for Generation IV Nuclear Energy System (2014), pp.

3. GIF (The Generation IV International Forum) and U.S DOE Nuclear Energy Research Advisory Committee, A technology Roadmap for Generation IV Nuclear Energy System (2002), pp.

4. R. D. Syarifah et al, “Comparison of Uranium and Thorium Nitride Fuel for 500MWth Gas Cooled Fast Reactor (GFR) Longlife without Refueling”, International Journal of Energy Research, Special Issue Paper, (2017), pp. 1–7.

5. Neutronic Analysis of Thorium Nitride (Th, U233)N Fuel for 500MWth Gas Cooled Fast Reactor (GFR) Long Life without Refueling

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