The Reactor Code DYN3DR - Transient Calculations of NEACRP Benchmarks for PWR and BWR


The Reactor Code DYN3DR - Transient Calculations of NEACRP Benchmarks for PWR and BWR

Grundmann, U.; Rohde, U.

The new version DYN3DR of the code DYN3D/M2, initially designed for hexagonal-z
core analysis, has been developed for reactor cores with rectangular fuel assemblies.
The neutronic part of the two code versions can be used for steady-state and transient
calculations of reactor cores. The neutron kinetics in both versions is based on the
solution of the two group neutron diffusion equation by nodal methods being different
for hexagonal and rectangular geometry. The thermal-hydraulic module FLOCAL
simulating the two phase flow of coolant and the fuel rod hehaviour is used in both
versions. The accuracy of DYN3DR is demonstrated by comparisons with rod ejection
benchmarks for a PWR with rectangular fuel assemblies. The two phase flow model of
FLOCAL also allows the simulation of BWR transients. Results for the transient BWR
benchmark initiated by increase of inlet subcooling are shown.

The neutron kinetic part is parallelized for running on SUN workstations with several
processors. The speedup for steady state neutronic calculations is presented.

  • Lecture (Conference)
    Jahrestagung Kerntechnik '96, Mannheim, 21. - 23. Mai 1996, Tagungsbericht S. 23 - 26
  • Contribution to proceedings
    Jahrestagung Kerntechnik '96, Mannheim, 21. - 23. Mai 1996, Tagungsbericht S. 23 - 26

Permalink: https://www.hzdr.de/publications/Publ-1727
Publ.-Id: 1727