Neutron kinetics of the Chernobyl accident
Description
The classical reactor kinetic equations with six groups of delayed neutrons are not solved analytically. Here they are solved numerically with MATLAB and applied to the Chernobyl accident. The results are presented graphically. Now, 20 years after the accident it is important for today's and tomorrow's generations of nuclear engineers to learn not to design reactors with runaway characteristics which can cause an avalanche like power excursion. The Chernobyl type of reactor has a positive void coefficient, which means that when a part of the water is replaced by steam the power will increase. At the Chernobyl experiment the steam content in the coolant channels increased suddenly causing a catastrophic power excursion. The presented analyses gives details about the importance of the magnitude of the void coefficient. Also the delayed neutrons behaviour is described. (orig.)
Additional details
Publishing Information
- Journal Title
- Atw. Internationale Zeitschrift fuer Kernenergie
- Journal Volume
- 51
- Journal Issue
- 4
- Journal Page Range
- p. 251-255
- ISSN
- 1431-5254
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 37065088
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CHERNOBYLSK-4 REACTOR; DELAYED NEUTRON PRECURSORS; DELAYED NEUTRONS; DIAGRAMS; MATRICES; REACTOR ACCIDENTS; REACTOR KINETICS; REACTOR KINETICS EQUATIONS; VOID COEFFICIENT; XENON OSCILLATIONS
- Descriptors DEC
- ACCIDENTS; BARYONS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; EQUATIONS; FERMIONS; FISSION NEUTRONS; GRAPHITE MODERATED REACTORS; HADRONS; INFORMATION; ISOTOPES; KINETICS; LWGR TYPE REACTORS; NEUTRONS; NUCLEONS; POISONING; POWER REACTORS; RADIOISOTOPES; REACTIVITY COEFFICIENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS