Abstract
The high-temperature gas-cooled reactor pebble-bed module (HTR-PM) nuclear power plant consists of two nuclear steam supply system modules, each of which drives the steam turbine by the superheated steam flow and is fed by the heated-up water flow. The shared steam/water system induces mutual effects on normal operation conditions and transients of the nuclear power plant, which is worthy of safety concerns and intensive study. In this paper, a coupling code package was developed with the TINTE and vPower codes to understand how the HTR-PM operated. The TINTE code was used to analyze the reactor core and primary circuit, while the vPower code simulated the steam/water flow in the conventional island. Two TINTE models were built and coupled to one vPower model through the data exchange in the steam generator models. Using this code package, two typical transients were simulated by decreasing the primary flow rate or introducing the negative reactivity of one module. Important parameters, including the reactor power, the fuel temperature, and the reactor inlet and outlet helium temperatures of two modules, had been studied. The calculation results preliminarily proved that this code package can be further used to evaluate working performance of the HTR-PM.
Highlights
Modular high-temperature gas-cooled reactor (HTR) is well-known for the high safety, high efficiency, and processing heat applications capability
E high-temperature gas-cooled reactor pebble-bed module (HTR-PM) nuclear power plant (NPP) consists of two nuclear steam supply system (NSSS) modules, each of which contains independent reactor core, steam generator (SG), and passive reactor cavity cooling system (RCCS). e steam generated in two NSSS modules is supplied to one steam turbine [2]
TINTE code is used to carry out the analysis of reactor core and primary circuit, while vPower code performs the secondary circuit calculation, including the primary side of the SGs. ese two codes are connected through components of SGs
Summary
Modular high-temperature gas-cooled reactor (HTR) is well-known for the high safety, high efficiency, and processing heat applications capability. The 600 MWe commercial NPP with six similar NSSS modules and only one steam turbine is in the standard design phase. With this typical multimodule design, the transient or perturbation in one module will inevitably influence the operating features of other modules. TINTE code is used to carry out the analysis of reactor core and primary circuit, while vPower code performs the secondary circuit calculation, including the primary side of the SGs. ese two codes are connected through components of SGs. In this paper, two cases, including the primary flow rate decrease and the reactivity introduction of one module, were simulated with this code package.
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