On numerical solution to the problem of reactor kinetics with delayed neutrons by Monte Carlo method

zbMath0812.65142MaRDI QIDQ1340148

Jan Kyncl

Publication date: 14 May 1995

Published in: Applications of Mathematics (Search for Journal in Brave)

Full work available at URL: https://eudml.org/doc/32883

zbMATH Keywords

Monte Carlo methodreactor kineticsintegral transport equation

Mathematics Subject Classification ID

Monte Carlo methods (65C05) Numerical methods for integral equations (65R20) Integro-partial differential equations (45K05) Transport processes in time-dependent statistical mechanics (82C70)

Cites Work

• Unnamed Item
• Time behavior of thermal neutrons in moderating media
• On Cauchy problem for the equations of reactor kinetics.

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