Citations (8)
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Read on this site (3)
Matjaž Ravnik & Robert Jeraj. (2003) Research Reactor Benchmarks. Nuclear Science and Engineering 145:1, pages 145-152.
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Tetsuo MATSUMOTO & Nobuhiro HAYAKAWA. (2000) Benchmark Analysis of TRIGA Mark II Reactivity Experiment Using a Continuous Energy Monte Carlo Code MCNP. Journal of Nuclear Science and Technology 37:12, pages 1082-1087.
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Yuichi KOMURO. (2000) A Proposal to Asian Countries with Operating Research Reactors for Making Nuclear Criticality Safety Benchmark Evaluations. Journal of Nuclear Science and Technology 37:6, pages 548-554.
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Articles from other publishers (5)
Fadi El Banni, Ouadie Kabach, Aka A. Koua, Bogbe L.H. Gogon, Georges A. Monnehan, Abdelfettah Benchrif, Hamid Amsil & Abdelouahed Chetaine. (2022)
Neutronic feasibility study of (
fuel in a modelled TRIGA research reactor
. Journal of King Saud University - Science 34:2, pages 101769.
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Ouadie Kabach, Abdelouahed Chetaine & Abdelfettah Benchrif. (2019) Processing of JEFF-3.3 and ENDF/B-VIII.0 and testing with critical benchmark experiments and TRIGA Mark II research reactor using MCNPX. Applied Radiation and Isotopes 150, pages 146-156.
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K Tiyapun & S Wetchagarun. (2017) Neutronics and thermal hydraulic analysis of TRIGA Mark II reactor using MCNPX and COOLOD-N2 computer code. Journal of Physics: Conference Series 860, pages 012035.
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Mohamad Hairie Rabir, Muhammad Rawi Md Zin, Mark Dennis Usang, Abi Muttaqin Jalal Bayar & Na’im Syauqi Bin Hamzah. Neutron flux and power in RTP core-15. Neutron flux and power in RTP core-15.
N. Catsaros, B. Gaveau, M.-T. Jaekel, J. Maillard, G. Maurel, P. Savva, J. Silva & M. Varvayanni. (2012) Building a dynamic code to simulate new reactor concepts. Nuclear Engineering and Design 246, pages 41-48.
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