The Verification of 3 Dimensional Nodal Kinetics Code ANCK Using Transient Benchmark Problems

Abstract

Three-dimensional (3D) neutronics and thermal-and-hydraulics (T/H) coupling code, ANCK/MIDAC, has been developed. ANCK/MIDAC consisted of the 3D nodal kinetic code ANCK and the 3D drift flux T/H code MIDAC. In order to verify the adequacy of ANCK that is a kinetics engine of this coupling code, several international benchmark problems have been performed. The calculation results of LMW (Langenbuch, Maurer and Werner) benchmark problems, PWR rod ejection benchmarks and PWR benchmarks on uncontrolled withdrawal of control rods at zero power are shown in this paper. The comparison of the results with the reference solutions shows very good agreements with the main core parameters.

Application of Backward Differentiation Formula to Spatial Reactor Kinetics Calculation With Adaptive Time Step Control

“…The two important transients of control rod ejection and uncontrolled withdrawal are examined with the NEACRP benchmark problem specification 7,8 . Note that these benchmark problems are used to demonstrate the transient capability of industry standard codes such as ANCK 14 . A more complete description of these benchmark problems and typical comparison results can be found elsewhere 11 .…”

Analysis of the SPERT-III E-Core Using ANCK Code with the Chord Weighting Method

“…The coupled 3D code ANCK/MIDAC 1,2) has been developed to provide best estimate and safety calculations for non-LOCA events. ANCK/MIDAC consists of the 3D nodal kinetic code ANCK 3) and the 3D drift flux thermal and hydraulics (T/H) code MIDAC.…”

Validation of Full Core Geometry Model of the Nodal3 Code in the PWR Transient Benchmark Problems

“…The calculated transient parameters by using NODAL3 code, such as maximum fuel temperature, time of power peak and final coolant temperature, will be compared with the reference solution results of the PANTHER code, which have been published in 1993 [1,11]. Beside the transient parameters, the boron concentration at criticality (static) parameter is also calculated.…”

“…Some previous research works showed that the analytical tool for analyzing the transient behaviour of a REA is the coupled neutronic thermal-hydraulic codes [1][2][3][4][5][6][7]. BATAN, as a research institute, has developed a coupled neutronic thermal-hydraulic (T/H) code, NODAL3, based on the nodal multi-group neutron diffusion method with 3-dimensional core geometry using polynomial nodal method [8].…”