Development of a computer code system for the analysis of prism and pebble type VHTR cores

Author:

Noh Jae Man,Kim Kang-Seog,Kim Yonghee,Lee Hyun Chul

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference18 articles.

1. Breismeister, J.F. et al., 1997. MCNP – A General Monte Carlo N-Particle Transport Code. Version 4B. LA-12625-M.

2. A study of nuclear hydrogen production demonstration plant;Chang;Nuclear Engineering and Technology,2007

3. Cho, B.O. et al., 1999. MASTER-2.0: Multi-purpose Analyzer for Static and Transient Effects of Reactors. Korea Atomic Energy Research Institute Technical Report (KAERI/TR-1211/99). Daejeon, Korea.

4. Halsall, M.J., 1996. WIMS7, an overview. In: Proceedings of International Conference on the Physics of Reactors (PHYSOR 96). Mito, Japan.

5. Hogenbirk, A. et al., 1995. HTR-Proteus Benchmark Calculations, Netherlands Energy Research Foundation (ECN) Technical Report (ECN-C–95-087). Petten, The Netherlands.

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