Temperature analysis of the HTR-10 after full load rejection

Zhang, Xiang-Cheng; She, Ding; Chen, Fu-Bing; Shi, Lei; Dong, Zhe; Zhang, Zuo-Yi

doi:10.1007/s41365-019-0692-1

Cited by 4 publications

(3 citation statements)

References 18 publications

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“…The safety basis of the pebble-bed modular HTGR is that even if a single-module reactor loses cooling, the maximum temperature of the fuel element does not exceed 1620 °C, solely due to the heat conduction and heat radiation from the pebble core [9,10]. For the HTR-PM600, the design parameters, operating parameters, design criteria of the reactor module, and the associated reactor cavity cooling system (RCCS) are exactly the same as those of the HTR-PM.…”

Section: Safetymentioning

confidence: 99%

600-MWe high-temperature gas-cooled reactor nuclear power plant HTR-PM600

Zhang

Dong

Shi³

et al. 2022

NUCL SCI TECH

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The HTR-PM600 high-temperature gas-cooled reactor nuclear power plant is based on the technology of the high-temperature gas-cooled reactor pebble-bed module (HTR-PM) demonstration project. It utilizes proven HTR-PM reactor and steam generator modules with a thermal power of 250 MWth and power generation of approximately 100 MWe per module. Six modules in parallel, connected to a steam turbine, form a 600-MWe nuclear power plant. In addition, its system configuration in the nuclear island is identical to that of the HTR-PM in which the technical risks are minimized. Under this principle, the HTR-PM600 achieves the same level of inherent safety as the HTR-PM. The concept of a ventilated low-pressure containment (VLPC) is unchanged; however, a large circular VLPC accommodating all six reactor modules is adopted rather than the previous small-cavity-type VLPC, which contains only one module, as defined for the HTR-PM. The layout of the nuclear island and its associated systems refer to single-unit pressurized water reactor (PWR) practices. With this layout, the HTR-PM600 achieves a volume size of the nuclear island that is comparable to a domestic PWR of the same power level. This will be a Generation IV nuclear energy technology that is economically competitive.

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Section: Safetymentioning

confidence: 99%

600-MWe high-temperature gas-cooled reactor nuclear power plant HTR-PM600

Zhang

Dong

Shi³

et al. 2022

NUCL SCI TECH

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“…Owing to their significant inherent safety and applicability characteristics, high-temperature gas-cooled reactors (HTGRs) have gradually played indispensable roles in nuclear reactor development [1][2][3]. HTGRs can be split into two types based on their core design: pebble-bed HTGRs, such as the high-temperature reactor pebble-bed module (HTR-PM) developed in China [4], and prismatic HTGRs, such as the modular high-temperature gas-cooled reactor (MHTGR-350), developed in the US [5].…”

Section: Introductionmentioning

confidence: 99%

keff uncertainty quantification and analysis due to nuclear data during the full lifetime burnup calculation for a small-sized prismatic high temperature gas-cooled reactor

et al. 2021

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To benefit from recent advances in modeling and computational algorithms, as well as the availability of new covariance data, sensitivity and uncertainty analyses are needed to quantify the impact of uncertain sources on the design parameters of small prismatic high-temperature gascooled reactors (HTGRs). In particular, the contribution of nuclear data to the k eff uncertainty is an important part of the uncertainty analysis of small-sized HTGR physical calculations. In this study, a small-sized HTGR designed by China Nuclear Power Engineering Co., Ltd. was selected for k eff uncertainty analysis during full lifetime burnup calculations. Models of the cold zero power (CZP) condition and full lifetime burnup process were constructed using the Reactor Monte Carlo Code RMC for neutron transport calculation, depletion calculation, and sensitivity and uncertainty analysis. For the sensitivity analysis, the Contribution-Linked eigenvalue sensitivity/Uncertainty estimation via Track length importance Characterization (CLUTCH) method was applied to obtain sensitive information, and the ''sandwich'' method was used to quantify the k eff uncertainty. We also compared the k eff uncertainties to other typical reactors. Our results show that 235 U is the largest contributor to k eff uncertainty for both the CZP and depletion conditions, while the contribution of 239 Pu is not very significant because of the design of low discharge burnup. It is worth noting that the radioactive capture reaction of 28 Si significantly contributes to the k eff uncertainty owing to its specific fuel design. However, the k eff uncertainty during the full lifetime depletion process was relatively stable, only increasing by 1.12% owing to the low discharge burnup design of small-sized HTGRs. These numerical results are beneficial for neutronics design and core parameters optimization in further uncertainty propagation and quantification study for small-sized HTGR.

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“…Among existing technology roadmaps of space nuclear reactors, the gas-cooled nuclear reactor combined with a closed Brayton cycle is perceived as the most rational scheme for the system power exceeding 200 kW [4][5][6]; this is because it can achieve a higher energy conversion efficiency and a smaller specific mass. Typically, pure helium is adopted as the working fluid for the terrestrial Brayton cycle because of its excellent thermal and transport properties [7]. However, its small molecular weight inevitably results in a larger aerodynamic loading of the turbomachinery, which in turn increases the mass and volume of the system [8].…”

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confidence: 99%

Nusselt number correlation for turbulent heat transfer of helium–xenon gas mixtures

Zhou

Sun

et al. 2021

NUCL SCI TECH

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A gas-cooled nuclear reactor combined with a Brayton cycle shows promise as a technology for high-power space nuclear power systems. Generally, a helium–xenon gas mixture with a molecular weight of 14.5–40.0 g/mol is adopted as the working fluid to reduce the mass and volume of the turbomachinery. The Prandtl number for helium–xenon mixtures with this recommended mixing ratio may be as low as 0.2. As the convective heat transfer is closely related to the Prandtl number, different heat transfer correlations are often needed for fluids with various Prandtl numbers. Previous studies have established heat transfer correlations for fluids with medium–high Prandtl numbers (such as air and water) and extremely low-Prandtl fluids (such as liquid metals); however, these correlations cannot be directly recommended for such helium–xenon mixtures without verification. This study initially assessed the applicability of existing Nusselt number correlations, finding that the selected correlations are unsuitable for helium–xenon mixtures. To establish a more general heat transfer correlation, a theoretical derivation was conducted using the turbulent boundary layer theory. Numerical simulations of turbulent heat transfer for helium–xenon mixtures were carried out using Ansys Fluent. Based on simulated results, the parameters in the derived heat transfer correlation are determined. It is found that calculations using the new correlation were in good agreement with the experimental data, verifying its applicability to the turbulent heat transfer for helium–xenon mixtures. The effect of variable gas properties on turbulent heat transfer was also analyzed, and a modified heat transfer correlation with the temperature ratio was established. Based on the working conditions adopted in this study, the numerical error of the property-variable heat transfer correlation was almost within 10%.

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Temperature analysis of the HTR-10 after full load rejection

Cited by 4 publications

References 18 publications

600-MWe high-temperature gas-cooled reactor nuclear power plant HTR-PM600

600-MWe high-temperature gas-cooled reactor nuclear power plant HTR-PM600

keff uncertainty quantification and analysis due to nuclear data during the full lifetime burnup calculation for a small-sized prismatic high temperature gas-cooled reactor

Nusselt number correlation for turbulent heat transfer of helium–xenon gas mixtures

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