# Research on the Dynamic Characteristics Analysis and Power Control Method of Heat Pipe Reactors
## 4 Research on Power Control Method of HPR
### TD3 Algorithm
* (3) [PERSON]; [PERSON] A reactor concept for space power employing thermionic diodes and heat pipes. In Proceedings of the 6 th Aerospace Sciences Meeting, New York, NY, USA, 22-24 January 1968* _[PERSON] and [PERSON] (1968)_ [PERSON]; [PERSON] A Nuclear Thermionic Space Power Concept Using Rod Control and Heat Pipes. _Nucl. Appl._**1968**, \(5\), 424-436. [CrossRef]
* _[PERSON] et al. (1977)_ [PERSON]; [PERSON]; [PERSON] Heat-Pipe Reactors for Space Power Applications. _J. Energy_**1977**, \(1\), 237-243. [CrossRef]
* _[PERSON] et al. (2000)_ [PERSON]; [PERSON]; [PERSON]; [PERSON] The Heatpipe Power System (HPS) for Mars outpose and manned Mars missions. In Proceedings of the Space Technology and Applications International Forum--2000, Albuquerque, NM, USA, 30 January-3 February 2000; pp. 1327-1334. * _[PERSON] (2000)_ [PERSON] The Heatpipe-Operated Mars Exploration Reactor (HOMER). AIP Conference Proceedings. In Proceedings of the Space Technology and Applications International Forum (STAIF-2000) on Space Exploration and Transportation--Journey into the Future, Albuquerque, NM, USA, 11-14 February 2001; pp. 797-804. * _El-Genk and Tournier (2004)_ [PERSON]; [PERSON]-M.P. \"SAIRS\"--Scalable Amtec Integrated Reactor space power System. _Prog. Nucl. Energy_**2004**, _45_, 25-69. [CrossRef]
* _El-Genk and Tournier (2004)_ [PERSON]; [PERSON] Conceptual Design of HP-STMCs Space Reactor Power System for 110 kWe. _AIP Conf. Proc._**2004**, _699_, 658-672. [CrossRef]
* _[PERSON] (2004)_ [PERSON] _The Martian Surface Reactor: An Advanced Nuclear Power Station for Manned Extraterrestrial Exploration_; Technical Report MIT-NSA-TR-003; Massachusetts Institute of Technology: Cambridge, MA, USA, 2004. * _[PERSON] (2012)_ [PERSON] _Final Results of Demonstration Using Flattop Fissions (DUFF) Experiment_; Technical Report LA-UR-12-25165; Los Alamos National Lab (LANL): Los Alamos, NM, USA, 2012. * _[PERSON] et al. (2019)_ [PERSON]; [PERSON] [PERSON] eVinciTM Micro Reactor. _Nuclear Plant J._**2019**, _37_, 34-37. * _[PERSON] et al. (2014)_ [PERSON]; [PERSON]; [PERSON]; [PERSON]; [PERSON] Experimental demonstration of a heat pipe-Stirling engine nuclear reactor. _Nucl. Technol._**2014**, _188_, 229-237. [CrossRef]
* _[PERSON] et al. (2020)_ [PERSON]; [PERSON] [PERSON]; [PERSON]; [PERSON] KRUSTY Reactor Design. _Nucl. Technol._**2020**, _206_, 13-30. [CrossRef]
* _[PERSON] et al. (2020)_ [PERSON]; [PERSON]; [PERSON]; [PERSON] Results of the KRUSTY Nuclear System Test. _Nucl. Technol._**2020**, _206_, 89-117. [CrossRef]
* _[PERSON] (2021)_ [PERSON]; [PERSON] A review of heat-pipe modeling and simulation approaches in nuclear systems design and analysis. _Ann. Nucl. Energy_**2021**, _160_, 108393. [CrossRef]
* _[PERSON] (1998)_ [PERSON]; [PERSON] A network thermodynamic analysis of the heat pipe. _Int. J. Heat Mass Transf._**1998**, _41_, 1473-1484. [CrossRef]
* _[PERSON] et al. (2022)_ [PERSON]; [PERSON]; [PERSON]; [PERSON] The Super Thermal Conductivity Model for High-Temperature Heat Pipe Applied to Heat Pipe Cooled Reactor. _Front. Energy Res._**2022**, _10_, 819033. [CrossRef]
* _[PERSON] et al. (2021)_ [PERSON]; [PERSON]; [PERSON] Numerical Modeling of a Wicked Heat Pipe Using Lumped Parameter Network Incorporating the Marangoni Effect. _HEAT Transfer. Eng._**2021**, _42_, 787-801. [CrossRef]
* _[PERSON] et al. (2021)_ [PERSON]; [PERSON]; [PERSON]; [PERSON]; [PERSON] High-fidelity multi-physics coupling study on advanced heat pipe reactor. _Comput. Phys. Commun._**2021**, _270_, 108152. [CrossRef]
* _[PERSON] et al. (2021)_ [PERSON]; [PERSON]; [PERSON]; [PERSON] A transient multiphysics coupling method based on OpenFOAM for heat pipe cooled reactors. _Sci. China Technol. Sci._**2021**, _65_, 102-114. [CrossRef]
* _[PERSON] et al. (2023)_ [PERSON]; [PERSON]; [PERSON]; [PERSON]; [PERSON] Multi-physics coupled simulation on steady-state and transients of heat pipe cooled reactor system. _Ann. Nucl. Energy_**2023**, _187_, 109774. [CrossRef]
* _[PERSON] (2019)_ [PERSON].