Advantages of going modular in HTRs

Reutler, H.; Lohnert, G.H.

doi:10.1016/0029-5493(84)90298-x

Cited by 126 publications

(28 citation statements)

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“…These small reactors are believed to fill a gap in the energy market as they may be constructed in a short time, can work on less developed energy grids and do not require the considerable upfront capital costs associated with currently operated large NPPs (nuclear power plants) that make purchasing them economically challenging for most countries [103][104][105][106][107][108][109][110][111][112][113][114][115][116]. Small modular reactors caused a similar euphoria in the 1960s and again in the 1980s that did not materialize due to the smaller reactors overall less favorable economic performance when compared to large (>1000 MWe) nuclear power plants (NPPs) [117,118] or other energy generating technology.…”

Section: Identified Challengesmentioning

confidence: 99%

On the Sustainability and Progress of Energy Neutral Mineral Processing

et al. 2018

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A number of primary ores such as phosphate rock, gold-, copper-and rare earth ores contain considerable amounts of accompanying uranium and other critical materials. Energy neutral mineral processing is the extraction of unconventional uranium during primary ore processing to use it, after enrichment and fuel production, to generate greenhouse gas lean energy in a nuclear reactor. Energy neutrality is reached if the energy produced from the extracted uranium is equal to or larger than the energy required for primary ore processing, uranium extraction, -conversion, -enrichment and -fuel production. This work discusses the sustainability of energy neutral mineral processing and provides an overview of the current progress of a multinational research project on that topic conducted under the umbrella of the International Atomic Energy Agency.

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Section: Identified Challengesmentioning

confidence: 99%

On the Sustainability and Progress of Energy Neutral Mineral Processing

et al. 2018

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“…Due to the low power density and large heat capacity, some SMRs even have the inherent safety feature which is the most advanced feature of these SMR-based plants relative to those conventional nuclear plants and also prevents these SMRs from the hazards of core-melting, radiological release and loss of coolant accident (LOCA) [3,4]. Due to the ability of offering simpler, safer and standardized modular design by factory-building, less initial capital investment, and shorter construction period, SMRs have been viewed by International Atomic Energy Agency (IAEA) as a developing trend of nuclear energy.…”

Section: Introductionmentioning

confidence: 99%

Model-Free Coordinated Control for MHTGR-Based Nuclear Steam Supply Systems

Dong

2016

Energies

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Abstract:The modular high temperature gas-cooled reactor (MHTGR) is a typical small modular reactor (SMR) that offers simpler, standardized and safer modular design by being factory built, requiring smaller initial capital investment, and having a shorter construction period. Thanks to its small size, the MHTGRs could be beneficial in providing electric power to remote areas that are deficient in transmission or distribution and in generating local power for large population centers. Based on the multi-modular operation scheme, the inherent safety feature of the MHTGRs can be applicable to large nuclear plants of any desired power rating. The MHTGR-based nuclear steam supplying system (NSSS) is constituted by an MHTGR, a side-by-side arranged helical-coil once-through steam generator (OTSG) and some connecting pipes. Due to the side-by-side arrangement, there is a tight coupling effect between the MHTGR and OTSG. Moreover, there always exists the parameter perturbation of the NSSSs. Thus, it is meaningful to study the model-free coordinated control of MHTGR-based NSSSs for safe, stable, robust and efficient operation. In this paper, a new model-free coordinated control strategy that regulates the nuclear power, MHTGR outlet helium temperature and OTSG outlet overheated steam temperature by properly adjusting the control rod position, helium flowrate and feed-water flowrate is established for the MHTGR-based NSSSs. Sufficient conditions for the globally asymptotic closed-loop stability is given. Finally, numerical simulation results in the cases of large range power decrease and increase illustrate the satisfactory performance of this newly-developed model-free coordinated NSSS control law.

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“…Hejzlar explored the feasibility of such concept based on light water reactor (LWR) design and concluded that the core with pressure tube and solid fuel matrix is the most preferable concept to design a practical reactor [1]. Reuter and Lohnert proposed a concept called modular high-temperature gas-cooled reactor (HTGR), which limits the core power density one order of magnitude less than that of conventional LWRs as well as utilizes the inherent characteristics of the inert, single-phase helium coolant, refractory-coated fuel particle, and heat-resistant graphite moderator [2]. These studies have focused on the development of a specific design concept and little attention has been given to the clarification of a design envelope against such accident, which are crucial for establishing a new design concept.…”

Section: Introductionmentioning

confidence: 99%

Thermal analysis of heated cylinder simulating nuclear reactor during loss of coolant accident

Satō

Ohashi

Tachibana

et al. 2014

Journal of Nuclear Science and Technology

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Transient analyses of temperature behavior of reactor during complete loss-of-coolant conditions throughout the entire period of accident with scram are presented. The influence of reactor thermal properties, operating power density, geometry of active core and selection of fuel type on the capability of decay heat removal against the accident are studied. It is shown that the reactor design envelope against loss-of-coolant accidents is fully determined by the key parameters: operating power density, volumetric heat capacity and thermal conductivity. The range of the envelope is shown to enlarge considerably by selecting high refractory fuel. Above 10% of operating power density in the current nuclear power plants, decay heat removal is not feasible without the presence of coolant in the reactor. The results suggest sufficient amount of solid materials, made of high-thermal conductance materials such as SiC and graphite, are required inside the reactor to achieve successful decay heat removal in loss-of-coolant accidents. High-temperature gas-cooled reactor, a graphite-moderated reactor with tristructural-isotropic (TRISO)-coated fuel particle, is the primary candidate which can fulfill the requirement to the design concept of nuclear reactor independent of coolant for decay heat removal.

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Advantages of going modular in HTRs

Cited by 126 publications

References 0 publications

On the Sustainability and Progress of Energy Neutral Mineral Processing

On the Sustainability and Progress of Energy Neutral Mineral Processing

Model-Free Coordinated Control for MHTGR-Based Nuclear Steam Supply Systems

Thermal analysis of heated cylinder simulating nuclear reactor during loss of coolant accident

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