Preliminary Study of a Prismatic-Core Advanced High-Temperature Reactor Fuel Using Homogenization Double-Heterogeneous Method

Author:

Alrwashdeh Mohammad1ORCID,Alameri Saeed A.1ORCID,Alkaabi Ahmed K.1ORCID

Affiliation:

1. Khalifa University of Science and Technology, Department of Nuclear Engineering, P.O. Box 127788, Abu Dhabi, United Arab Emirates

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Reference14 articles.

1. Prismatic-core advanced high temperature reactor and thermal energy storage coupled system – A preliminary design

2. G. MARLEAU, A. HEBERT, and R. ROY, “A User Guide for DRAGON 3.05 C.  Report IGE-174 Rev. 6C,” Institut de génie nucléaire, École Polytechnique de Montréal, Québec (2006).

3. G. MARLEAU, A. HÉBERT, and R. ROY, “New Computational Methods Used in the Lattice Code DRAGON,” CONF-920308, Vol. 1, Proceedings of the 1992 Topical Meeting on Advances in Reactor Physics, American Nuclear Society,  March 8–11, 1992, Charleston, NC (1992).

4. Y. KIM and M. BAEK, “Elimination of Double-Heterogeneity Through a Reactivity Equivalent Physical Transformation,” GLOBAL 2005: Proceedings of the International Conference on Nuclear Energy Systems for Future Generation and Global Sustainability, Atomic Energy Society of Japan, p. 2562, October 9–13, Tsukuba, Japan (2005).

5. T. A. TAIWO and T. K. KIM, “Evaluation of the DRAGON Code for VHTR Design Analysis,” ANL-GENIV-060, Argonne National Laboratory (2006).

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