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82D75 Nuclear reactor theory; neutron transport (6 articles)

• Abdelmoumen, Boulbeba; Jedidi, Omar; Jeribi, Aref: Time asymptotic description of an abstract Cauchy problem solution and application to transport equation. (English). Applications of Mathematics, vol. 59 (2014), issue 1, pp. 53-67
• Hanuš, Milan: A new perspective on some approximations used in neutron transport modeling. (English). In: Chleboun, J., Segeth, K., Šístek, J. and Vejchodský, T. (eds.): Programs and Algorithms of Numerical Mathematics. Proceedings of Seminar. Dolní Maxov, June 3-8, 2012. Institute of Mathematics AS CR, Prague, 2013. pp. 81-87
• Berka, Tomáš; Brandner, Marek; Hanuš, Milan; Kužel, Roman; Matas, Aleš: Numerical modeling of neutron flux in hexagonal geometry. (English). In: Chleboun, J., Přikryl, P., Segeth, K. and Vejchodský, T. (eds.): Programs and Algorithms of Numerical Mathematics. Proceedings of Seminar. Dolní Maxov, June 1-6, 2008. Institute of Mathematics AS CR, Prague, 2008. pp. 15-22
• Hanuš, Milan; Berka, Tomáš; Brandner, Marek; Kužel, Roman; Matas, Aleš: Three-dimensional numerical model of neutron flux in hex-Z geometry. (English). In: Chleboun, J., Přikryl, P., Segeth, K. and Vejchodský, T. (eds.): Programs and Algorithms of Numerical Mathematics. Proceedings of Seminar. Dolní Maxov, June 1-6, 2008. Institute of Mathematics AS CR, Prague, 2008. pp. 83-90
• Ratemi, Wajdi A.: RTC-method for the control of nuclear reactor power. (English). Kybernetika, vol. 34 (1998), issue 2, pp. [189]-198
• Zezula, Rostislav: Criticality conditions for a finite homogenized natural-uranium fueled reactor with prescribed thermal neutron flux. (English). Aplikace matematiky, vol. 15 (1970), issue 5, pp. 328-338