A Linear Stability Analysis of Supercritical Water Reactors, (II) : Coupled Neutronic Thermal-Hydraulic Stability

概要

論文の詳細を見る
A mathematical model is developed to study the coupled neuronic thermal-hydraulic stability for a high-temperature reactor cooled and moderated by supercritical-pressure light water (SCLWR-H). The present model incorporates coolant and fuel dynamics as well as reactor neutronics. One-dimensional single-channel single-phase conservation equations are used in the thermal-hydraulics model and point-kinetics approximation is used in the reactor neutronics model. One-dimensional heat conduction equations are used in heat transfer model. The water rod thermal-hydraulic model and heat transfer model are included to study the effects of water rods on reactor stability. The stability of SCLWR-H for full-power and partial-power normal operation is investigated by frequency domain linear stability analysis. The decay ratio for coupled neutronic thermal-hydraulic stability of SCLWR-H is considerable due to the time delay of the heat transfer to the water rod. The stability criterion can be satisfied at normal operation. The sensitivity of the coupled neutronic thermal-hydraulic stability to various operating conditions and design parameters is also studied.
社団法人日本原子力学会の論文
2004-12-25