Published March 2009 | Version v1
Journal article

Analysis of the SPERT-III E-core using ANCK code with the chord weighting method

  • 1. Mitsubishi Heavy Industries, Ltd., Kobe, Hyogo (Japan)
  • 2. Osaka Univ., Suita, Osaka (JP)

Description

ANCK/MIDAC is a three-dimensional (3D) code system that has been developed, which couples the 3D nodal kinetic code ANCK and the 3D drift flux thermal-and-hydraulics (T/H) code MIDAC. The adequacy of the ANCK feedback model was confirmed by analysis of the SPERT-III E-core reactivity accident tests. The chord weighting method was adopted in the effective fuel temperature (Teff) calculation model of ANCK and ANCK/MIDAC since it provides results that are in good agreement with those of a Monte Carlo calculation. The adequacy of the Teff model was also confirmed. The calculation results for hot startup and hot standby conditions using the ANCK code showed excellent agreement for the main parameters such as peak power, peak time, and behavior of reactor power. It was also confirmed that the ANCK feedback model with the chord weighting method was applicable to the reactivity-initiated accident (RIA) calculation for the case of 4.8 wt% UO2 core. (author)

Additional details

Identifiers

Publishing Information

Journal Title
Journal of Nuclear Science and Technology (Tokyo)
Journal Volume
46
Journal Issue
3
Journal Page Range
p. 239-251
ISSN
0022-3131

Optional Information

Notes
Available from doi: http://dx.doi.org/10.3327/jnst.46.239; 26 refs., 25 figs., 5 tabs.