Design of High Temperature Engineering Test Reactor (HTTR)

Fujiwara, Yusuke; Goto, Minoru; Iigaki, Kazuhiko; Iyoku, Tatsuo; Ho, Hai Quan; Kawamoto, Taiki; Kondō, Makoto; Kunitomi, Kazuhiko; Morita, Kenichi; Nagasumi, Satoru; Nakagawa, Shigeaki; Nishihara, Tetsuo; Nojiri, Naoki; Ono, Masato; Saikusa, Akio; Sakaba, Nariaki; Shibata, Taiju; Shimazaki, Yasuhisa; Shimizu, Atsushi; Shinozaki, Masayuki; Sumita, Junya; Tachibana, Yukio; Shoji, T.; Tochio, Daisuke; Uesaka, Takahiro; Ueta, Shohei

doi:10.1016/b978-0-12-821031-4.00002-6

Cited by 5 publications

(3 citation statements)

References 47 publications

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“…In one fuel column, there are four replaceable reflector blocks above and below five fuel blocks. Replaceable and permanent reflector blocks surround the active core 20 …”

Section: Design Conceptmentioning

confidence: 99%

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Comparison of neutronic aspects in high‐temperature gas‐cooled reactor using ZrC and SiC Triso particle with 50 and 100 MWt power

Miftasani

Su’ud

Irwanto

et al. 2021

Intl J of Energy Research

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Summary The use of zirconium carbide (ZrC) as a substitute for silicon carbide (SiC) has been proposed to improve the performance of coated particles for high‐temperature gas‐cooled reactor (HTGR) fuel. Irradiation test on ZrC has proved that it has excellent characteristics for HTGR fuel compared with SiC, such as fission product retention capabilities and better resistance on fission product corrosion. Neutronic analysis on 30 MWt HTGR using ZrC and SiC has been performed in many previous studies. The research presented in this paper was conducted as a further continuation of the aforementioned studies. The present study was directed to analyze tristructural isotropic (TRISO)‐coated particles with ZrC as a substitute for the SiC layer on an HTGR with different power rates. Here, we used high‐temperature test reactor design, an experimental scale prismatic HTGR built and operated in Japan. The power was varied at the range of 50‐100 MWt, while the reactor geometry was modified by applying an additional fuel layer in the axial and radial directions. Neutronic analysis of the reactor was investigated by calculating the k‐eff, k‐inf, power peaking factor, burn‐up level, neutron spectrum, and Doppler effect using ZrC and SiC layers for TRISO‐coated fuel particles. The result shows the coated fuel particle using the ZrC layer has the same performance as SiC with an insignificant difference in the values on neutronic aspects calculation. Neutronic calculations are performed using the SRAC code with the Japanese Evaluated Nuclear Data Library 4.0 nuclear data library.

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“…In one fuel column, there are four replaceable reflector blocks above and below five fuel blocks. Replaceable and permanent reflector blocks surround the active core 20 …”

Section: Design Conceptmentioning

confidence: 99%

“…Replaceable and permanent reflector blocks surround the active core. 20 The fuel blocks consist of 30 fuel rods that consist of fuel compact. Fuel compacts are graphite matrix dispersed, and each compact consists of about 13 000 coated fuel particles with 0.92 mm diameter, as shown in Figure 2.…”

Section: Design Optimization and Enrichment Zoningmentioning

confidence: 99%

Comparison of neutronic aspects in high‐temperature gas‐cooled reactor using ZrC and SiC Triso particle with 50 and 100 MWt power

Miftasani

Su’ud

Irwanto

et al. 2021

Intl J of Energy Research

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“…Certain engineering systems function in a passive manner, such as pressure relief valves. Both necessitate the integration of parallel redundancy systems [90,91]. The inherent or full passive safety design relies solely on physical phenomena, such as convection, gravity, or resistance to high temperatures, rather than the operation of manufactured components [92,93].…”

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confidence: 99%

Selected Legal and Safety Aspects of the “Coal-To-Nuclear” Strategy in Poland

Chmielewska-Śmietanko,

Miśkiewicz,

Smoliński

et al. 2024

Energies

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Poland is actively exploring the application of nuclear power as a substitute for its present reliance on fossil fuels for the generation of heat and electricity. This change reflects a calculated attempt to reduce carbon emissions, diversify the nation’s energy sources, and enhance the sustainability of its energy infrastructure. However, the implementation of nuclear technology faces many challenges, such as radiation exposure, the production of radioactive waste, the off-site effects of nuclear accidents, and high capital costs. Addressing such nuclear-safety-related issues is crucial for nuclear technology’s successful deployment. An extended analysis of the “coal-to-nuclear” process in terms of its safety has to be performed. Therefore, this review paper covers multidisciplinary studies related to the rollout of nuclear energy in Poland. The first stage of this study was the identification of the key areas of analysis, which included (i) formal requirements and recommendations imposed by international and national organizations on the process of designing and operating nuclear power systems; (ii) potential nuclear hazards for the personnel working at a nuclear reactor unit and the local population; (iii) the applied solutions of the security systems of a reactor itself, the steam turbine cycle, and the auxiliary infrastructure; and (iv) the management of spent nuclear fuel and radioactive waste. This methodology, developed based on a review of the literature and international standards, was tested for the selected country—Poland.

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