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High-Temperature Reactors
Published in William J. Nuttall, Nuclear Renaissance, 2022
The reactor core has a diameter of 1.8 m and a mean height of 1.97 m. It is surrounded by graphite reflectors. The HTR-10 has a thermal power of 10 MW. The outer reflector blocks are boronated to provide thermal and neutron shielding to metallic internal components and to the reactor pressure vessel [108].
Modular Nuclear Reactors
Published in Yatish T. Shah, Modular Systems for Energy and Fuel Recovery and Conversion, 2019
China’s HTR-10, a 10 MWt high-temperature gas-cooled experimental reactor at the Institute of Nuclear Energy Technology (INET) at Tsinghua University, started up in 2000 and reached full power in 2003. It has its fuel as a “pebble bed” (27,000 elements) of oxide fuel with average burn-up of 80 GWd/tU. Each pebble fuel element has 5 g of uranium enriched to 17% in around 8,300 TRISO-coated particles. The reactor operates at 700°C (potentially 900°C) and has broad research purposes. Eventually, it will be coupled to a gas turbine, but meanwhile, it has been driving a steam turbine. In 2004, six successful safety demonstration tests were performed on small HTR-10 reactor [12,41–43,46,55,85].
High-Fidelity Neutron Transport Solution of High Temperature Gas-Cooled Reactor by Three-Dimensional Linear Source Method of Characteristics
Published in Nuclear Science and Engineering, 2023
Kaijie Zhu, Boran Kong, Han Zhang, Jiong Guo, Fu Li
The HTR-10 is an experimental modular pebble-bed reactor with a thermal power of 10 MW built at the INET, Tsinghua University, China. In this section, a simplified initial criticality HTR-10 problem is used to demonstrate the capability of the ARCHER code when applied to practical large-scale pebble-bed problems. The graphite pebbles, fuel pebbles with a homogenized matrix region, and helium flow area are explicitly modeled in the reactor active core. It is noted that the helium flow area in the core is filled with a vacuum medium whose cross sections are assigned to be zero. There are 28 649 pebbles randomly piled in the active core, and the proportion of fuel pebbles is about 57%. The side reflector, cold helium channels, absorb ball channels, and control rod channels are also accurately constructed. All of the channels in the reflector core are filled with the vacuum medium. The four-group cross sections without transport correction produced by VSOP are used to conduct the transport calculation. Although, four-group cross sections are not enough to obtain sufficiently accurate results, they have a low computing cost when comparing the calculation parameters required to achieve spatial convergence between FSA and LSA. In a future study, both more refined cross sections and transport correction will be taken into account. The XY and RZ cross-sectional views of this simplified HTR-10 problem are shown in Fig. 6.
Scaling Analysis of Reactor Cavity Cooling System in HTR
Published in Nuclear Technology, 2020
Thiago D. Roberto, Celso M. F. Lapa, Antonio C. M. Alvim
The 10-MW(thermal) high-temperature gas-cooled test reactor (HTR-10) is a graphite-moderated helium-cooled generation IV reactor with a thermal neutron spectrum and a pebble-bed core that represents one of the possible concepts of a very high temperature reactor (VHTR). This reactor configuration can provide a core outlet temperature ranging from 700°C to 950°C. This high-temperature pebble-bed core reactor concept includes a containment structure made of reinforced concrete. The integrity of this containment structure needs to be ensured to prevent site-induced accidents. The temperature of the concrete containment structures must be maintained below 70°C under any operating condition.1 Thus, the concrete structure needs to be cooled by a reactor cavity cooling system (RCCS) that can guarantee the physical integrity of the cavity.
Neutronics Analysis for a High-Temperature Gas-Cooled Reactor in a Water-Flooded-Core Accident
Published in Nuclear Technology, 2020
Zhong Chen, Zi Jia Zhao, Zhongliang Lv, Yanyun Ma
For the HTR-10, its primary helium pressure is designed to be 3 MPa, the helium inlet temperature is designed to be 250°C, and the helium outlet temperature is designed to be 700°C. It is obvious that the primary helium pressure and the helium temperatures are different from the analysis in Secs. III.C.1 and III.C.2. Then, the preliminary temperature effect analysis is performed on the HTR-10 core as well. In our study, the operation temperature of the HTR-10 is assumed to be 627°C (900 K). According to document IAPWS-1F97 (1997) of the International Association for the Properties of Water and Steam Formulation, the water is vaporous water under the operation temperature. If the vaporous water is assumed to be ideal gas, its nucleon density could be employed as