Published June 2017
| Version v1
Journal article
Results of two-dimensional hexagonal dynamic benchmark problems solved using diffusion kinetic code
Creators
- 1. Reactor Physics and Nuclear Engineering Section, Bhabha Atomic Research Centre, Mumbai (India)
Description
A two-dimensional nodal kinetics code was developed to solve for the time-dependent neutron diffusion equation in the hexagonal geometry. Direct space time method was used for solving the time-dependent multi-group diffusion equation. The space part was solved using higher order nodal expansion method, wherein one-dimensional neutron flux in each node and energy group was approximated using higher order polynomial, while the first-order time derivative was approximated by finite difference implicit scheme. The code was used to solve two problems based on (1) VVER-440 and (2) HWR. (author)
Additional details
Publishing Information
- Journal Title
- SRESA's International Journal of Life Cycle Reliability and Safety Engineering
- Journal Volume
- 6
- Journal Issue
- 2
- Journal Page Range
- p. 141-147
- ISSN
- 2250-0820
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 48092349
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BENCHMARKS; CROSS SECTIONS; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; NODAL EXPANSION METHOD; REACTOR SAFETY
- Descriptors DEC
- CALCULATION METHODS; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; EQUATIONS; PARTIAL DIFFERENTIAL EQUATIONS; RADIATION FLUX; SAFETY
Optional Information
- Notes
- 8 refs., 7 figs.