Evaluation of core thermal and hydraulic characteristics of HTTR

Maruyama, S.; Fujimoto, Nozomu; Sudo, Yukio; Murakami, Tomoyuki; Fujii, Sadao

doi:10.1016/0029-5493(94)90084-1

Cited by 15 publications

(4 citation statements)

References 4 publications

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“…In the safety requirements of HTGR, the maximum fuel temperature was determined based on the criterion that the coating layer of fuel particles must remain on the particles and retain fission products within the particles. The maximum fuel temperature should be under an acceptable level at 1,495 o C during normal operation and not exceed 1,600 o C during any anticipated accident (Maruyama et al, 1994;Takada et al, 2004).…”

Section: Description Of the Reactormentioning

confidence: 99%

Concept of prismatic high temperature gas-cooled reactor with SiC coating on graphite structures

Trinuruk

Obara

2014

Annals of Nuclear Energy

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A 100-MW th prismatic high temperature gas-cooled reactor was designed to be a long-life small reactor. To acquire a passive safety feature, the reactor was mainly improved with regard to graphite oxidation resistance. The concept of applying a silicon carbide coating layer on the surface of the graphite structures in the core was proposed to overcome any serious problem from graphite oxidation during unforeseen situations. However, there was concern that the deviation of neutronic and thermal properties of silicon carbide from graphite could affect the reactor operation and the heat transfer characteristics. Therefore, in this study we investigated the effects of applying a silicon carbide coating layer over the graphite structures from the neutronic and thermal-hydraulic points of view. Silicon carbide coating can lower the effective multiplication factor and shorten the reactor operating cycle, but not significantly. From the viewpoint of thermal-hydraulic operation, silicon carbide has lower thermal conductivity than that of graphite, so the layer of silicon carbide could act as a wall to keep the heat from moving across the layer. Under normal operation, the layer of silicon carbide coating had a less significant impact on the maximum fuel temperature, and the temperature remained lower than

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Section: Description Of the Reactormentioning

confidence: 99%

Concept of prismatic high temperature gas-cooled reactor with SiC coating on graphite structures

Trinuruk

Obara

2014

Annals of Nuclear Energy

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“…Before the implementation of annular fuels into the HTTR, the computational result (Maruyama et al, 1994) of the HTTR from JAERI was compared with that from Korea Advanced Institute of Science and Technology (KAIST). The dimension of graphite block and fuel element, and the operating condition of HTTR are given in Fig.…”

Section: Calculation Of Httrmentioning

confidence: 99%

“…The most limiting core design require- (Maruyama et al, 1994), fuel design limit for anticipated operational occurrences and fuel temperature limit for normal operation are specified at 1600 and 1495 • C, respectively. At normal operation, design options, which allow an increase in the average coolant outlet temperature to 1000 • C while maintaining fuel temperatures at acceptable levels, include reducing bypass flow and controlling flow distribution.…”

Section: Introductionmentioning

confidence: 99%

Development of a thermal hydraulic analysis code for gas-cooled reactors with annular fuels

Han

Seo

Hwang

et al. 2006

Nuclear Engineering and Design

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“…Coolant pressure and temperatures are as follows: 4 MPa and 395 °C/850 °C-950 °C. Thermal output reaches 30 MW (Maruyama et al, 1994). Based on the HTTR project, JAERI is developing the Gas Turbine High Temperature Reactor (GT-HTR) of thermal power up to 600 MWt per module.…”

Section: Introductionmentioning

confidence: 99%

Developing PCC and DCC integral effects test experiments at the High Temperature Test Facility

2023

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Among the Next-Generation Nuclear Plant (NGNP) designs, the High-Temperature Gas-Cooled Reactors (HTGRs) are very attractive, due to their inherent safety features, high power conversion efficiency, and potential of providing high-temperature process heat. To perform a thorough safety study and to license these types of reactors, sufficient information needs to be provided about the phenomena that occur during accident scenarios. While several experimental research efforts have been dedicated in the past to investigate accident scenarios, knowledge gaps still exist in the phenomena characteristic of pressurized and depressurized conduction cooldown (PCC/DCC) transients as well as for normal operation scenarios. This paper summarizes the Oregon State University High Temperature Test Facility (HTTF) test matrix, experimental campaign, and selected tests results. High Temperature Test Facility is a scaled Integral Test Facility (IET) that is capable of mimicking scaled dimensions and operational conditions of the Modular High-Temperature Gas Cooled Reactor (MHTGR). The goal of the High Temperature Test Facility is to provide experimental data on the DCC, PCC and normal operating scenarios of the reference Modular High-Temperature Gas Cooled Reactor design. The DCC, PCC, mixing, heat up and cooldown tests described in this paper were performed at prototypical Modular High-Temperature Gas Cooled Reactor temperatures, scaled initial pressure conditions (∼200 kPa), and thermal power input of less than 70 kW. Presented test data show temperature distributions in the High Temperature Test Facility core, upper plenum, cross duct, or lower plenum. Based on these temperature profiles attempts to investigate stratified flow, natural convection flow, heat up, cooldown and mixing phenomena are made. Furthermore, this paper evaluates the performed test campaign in the light of the Very High Temperature Gas-cooled Reactor Phenomena Identification and Ranking Table (PIRT) and proposes experiments to complement the existing PCC/DCC testing database for the validation of the thermal-hydraulic codes.

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Evaluation of core thermal and hydraulic characteristics of HTTR

Cited by 15 publications

References 4 publications

Concept of prismatic high temperature gas-cooled reactor with SiC coating on graphite structures

Concept of prismatic high temperature gas-cooled reactor with SiC coating on graphite structures

Development of a thermal hydraulic analysis code for gas-cooled reactors with annular fuels

Developing PCC and DCC integral effects test experiments at the High Temperature Test Facility

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