A review and safety aspects of modularhigh‐temperature gas‐cooledreactors

Abstract

Summary Modular high‐temperature gas‐cooled reactor (MHTGR) is being developed under the Next Generation Nuclear Plant Program in nuclear engineering studies. As the world searches for an energy source with high energy density, clean, abundant, and storable nature to avoid global warming issues, MHTGR seems to be a promising solution, particularly the possibility of producing hydrogen. Studying and developing safety analyses are required for the optimum design and safety of the MHTGR systems. The focus of several researchers, in previous years, has been directed in conducting investigations on natural convection heat transfer and flow dynamics in diverse geometries and operating conditions of MHTGR. The implementation of natural convection in nuclear reactors comes in the form of an engineered feature in accomplishing passive safety. In this review article, a comprehensive literature review has been introduced about the current status of the MHTGR. As part of an effort to understand the current status of the MHTGR safety analysis technology, this article introduced the MHTGR phenomena identification and event categorization and acceptance criteria.

Fractional‐order sliding mode load following control via disturbance observer for modular high‐temperature gas‐cooled reactor system with disturbances

“…The safety of nuclear power has become a major issue restricting the development of nuclear power. It is known that MHTGRs feature the inherent safety, versatility, and economy, and thus, the MHTGR-type nuclear power plants have been extensively concerned at home and abroad [32]. The uncertain MHTGR model is expressed as follows [33]:…”

“…The safety of nuclear power has become a major issue restricting the development of nuclear power. It is known that MHTGRs feature the inherent safety, versatility, and economy, and thus, the MHTGR‐type nuclear power plants have been extensively concerned at home and abroad [32]. The uncertain MHTGR model is expressed as follows [33]: $$$$ \left\{\begin{array}{ll}{\dot{n}}_r&...$$…”

Effects of the central graphite column dimension and pebble size on power density distribution in annular core pebble‐bed HTR

“…Since a small modular high‐temperature gas‐cooled pebble‐bed reactor 1 can have a negative temperature coefficient and excellent heat conductivity in the accident scene, 2 the German SIEMENS/INTERATOM had demonstrated the inherent safety features and designs of the small Modular HTGR 3 . Therefore, regarded as one of the most promising technology in generation IV nuclear power systems, small modular HTGR has been drawn significant attention.…”

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

“…HTGR is included in designing of a future NES being researched which is referred to as the Generation IV reactor (Gen IV). Other Gen IV reactors are supercritical‐water‐cooled reactor (SCWR), molten salt reactor (MSR), and fast reactors such as sodium‐cooled reactor and lead fast reactor 2 . Some previous studies have been conducted to evaluate the reactor performances based on generation IV (Gen IV) reactors which can be compared with others previous generation of nuclear power such as liquid metal fast reactors, MSR as well as HTGR and some experimental for evaluating the natural circulation for advanced reactor 3–6 …”

“…In addition, from the aspect of cooling material, the use of helium in HTGR as a coolant has its advantages compared to other gases, for example, CO 2 . Helium has high corrosion resistance, although helium gas needs to be purified before being used as a coolant 2 . The fuel material used in HTGR is commonly uranium dioxide.…”