Abstract
The modular high temperature gas-cooled reactor (MHTGR) is a typical small modular reactor (SMR) with inherent safety feature. Due to its high reactor outlet coolant temperature, the MHTGR can be applied not only for electricity production but also as a heat source for industrial complexes. Through multimodular scheme, that is, the superheated steam flows produced by multiple MHTGR-based nuclear supplying system (NSSS) modules combined together to drive a common thermal load, the inherent safety feature of MHTGR is applicable to large-scale nuclear plants at any desired power ratings. Since the plant power control technique of traditional single-modular nuclear plants cannot be directly applied to the multimodular plants, it is necessary to develop the power control method of multimodular plants, where dynamical modeling, control design, and performance verification are three main aspects of developing plant control method. In this paper, the study in the power control for two-modular HTR-PM plant is summarized, and the verification results based on numerical simulation are given. The simulation results in the cases of plant power step and ramp show that the plant control characteristics are satisfactory.
Highlights
With comparison to burning fossil fuels, there is nearly no greenhouse gas emission in nuclear fission reaction
The HTR-PM plant remains at the steady state of 100% plant full power (PFP) which means that the two nuclear supplying system (NSSS) modules are running at the 100% reactor full power (RFP)
The HTR-PM plant remains at the steady state of 95% PFP; that is, the two NSSS modules operate at 95% RFP
Summary
With comparison to burning fossil fuels, there is nearly no greenhouse gas emission in nuclear fission reaction. Due to its inherent safety feature, the modular high temperature gas-cooled reactor (MHTGR, such as HTR-Module designed in Germany and MHTGR designed in US) has been seen as one of the best candidates for the nextgeneration nuclear plants. China began to study the MHTGR at the end of 1970s, and a 10 MWth pebble-bed high temperature gas-cooled reactor HTR-10, which was designed by the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University, achieved its criticality in December 2000 and full power in January 2003 [11]. Based on the experience of the HTR-10 project, a high temperature gas-cooled reactor pebble-bed module (HTRPM) plant was proposed, which consists of two pebblebed one-zone MHTGRs with combined 2 × 250 MWth power and adopts the operation scheme of two NSSS modules driving one steam turbine [13, 14]. The pressure loss of the primary helium flow is very small with comparison to the primary pressure and is omitted here
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