Study on air ingress during an early stage of a primary-pipe rupture accident of a high-temperature gas-cooled reactor

Hishida, Makoto; Takeda, Tetsuaki

doi:10.1016/0029-5493(91)90109-u

Cited by 23 publications

(12 citation statements)

References 1 publication

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“…The capability of RELAP5-3D to represent both phenomena was assessed. The diffusion model was assessed using data from inverted U-tube experiments (Hishida and Takeda 1991). The code capability to simulate the natural circulation of air through a pebble bed was assessed using data from the NACOK facility (Kuhlmann 2003).…”

Section: Task 4: Improvement Of System Codes (Ineel)mentioning

confidence: 99%

“…The experimental apparatus of Hishida and Takeda (1991) is shown in Figure 4-1. The apparatus consisted of an inverted U-tube, ball valves, and a tank.…”

Section: Assessment Of the Molecular Diffusion Modelmentioning

confidence: 99%

“…The RELAP5 model shown in Figure 4-2 is much more detailed than typical reactor models and consists of 144 control volumes, most of which are 2.45 cm long. The nodalization is similar to that used previously by Hishida and Takeda (1991) and Lim and No (2003). RELAP5 calculations were performed for both the isothermal and non-isothermal experiments.…”

Section: Assessment Of the Molecular Diffusion Modelmentioning

confidence: 99%

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Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-Cooled Reactor

Chang¹,

Davis²,

Moore³

2004

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Section: Task 4: Improvement Of System Codes (Ineel)mentioning

confidence: 99%

“…The experimental apparatus of Hishida and Takeda (1991) is shown in Figure 4-1. The apparatus consisted of an inverted U-tube, ball valves, and a tank.…”

Section: Assessment Of the Molecular Diffusion Modelmentioning

confidence: 99%

Section: Assessment Of the Molecular Diffusion Modelmentioning

confidence: 99%

See 1 more Smart Citation

Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-Cooled Reactor

Chang¹,

Davis²,

Moore³

2004

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“…The first is done in Japan by JAERI in which a series of three experiments were conducted in sequential order to develop a fundamental understanding of the three key phenomenon [3] …”

Section: Introductionmentioning

confidence: 99%

Air ingress benchmarking with computational fluid dynamics analysis

Kadak

Zhai

2006

Nuclear Engineering and Design

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Air ingress accident is a complicated accident scenario that may limit the deployment of hightemperature gas reactors. The complexity of this accident scenario is compounded by multiple physical phenomena that are involved in the air ingress event. These include diffusion, natural circulation, and complex chemicals reaction with graphite and oxygen. In an attempt to better understand the phenomenon, the FLUENT-6 computational fluid dynamics code was used to assess two air ingress experiments. The first was the Japanese series of tests on the reference performed in the early 1990's by Takeda and Hishida. These separate effects tests were conducted to understand and model the a multi-component experiment in which all three processes were included with the introduction of air in a heated graphite column. MIT used the FLUENT code to benchmark these series of tests with quite good results. These tests are generically applicable to prismatic reactors and the lower reflector regions of pebble-bed reactors. The second series of tests were performed at the NACOK facility for pebble bed reactors as reported by M. B. Kuhlmann in 1999. This tests were aimed at understanding natural circulation of pebble bed reactors by simulating hot and cold legs of these reactors. The FLUENT code was also successfully used to simulate these tests. The results of these benchmarks and the findings will be presented.

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“…The main responsible phenomenon is the persistence of a helium -bubble‖ in the top area of the vessel, which inhibits recirculation flows within the core. Experiments and analyses by JAERI 14 and others have shown that this bubble may be effectively maintained in the vessel for days. For idealized experimental conditions, these predictions have proven quite accurate.…”

Section: Air Ingressmentioning

confidence: 99%

HTGR Measurements and Instrumentation Systems

Holcomb

Çetiner

2012

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Study on air ingress during an early stage of a primary-pipe rupture accident of a high-temperature gas-cooled reactor

Cited by 23 publications

References 1 publication

Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-Cooled Reactor

Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-Cooled Reactor

Air ingress benchmarking with computational fluid dynamics analysis

HTGR Measurements and Instrumentation Systems

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