Leak-tightness characteristics concerning the containment structures of the HTTR

Sakaba, Nariaki; Iigaki, Kazuhiko; Kondo, Masaaki; Emori, Koichi

doi:10.1016/j.nucengdes.2004.08.023

Cited by 8 publications

(3 citation statements)

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“…In the compositions used in the evaluation models, the natural-boron content is adjusted to include only the primary absorber 10 B, according to the isotopic abundance of 19.9 at.%.…”

Section: Evaluation Of Critical and / Or Subcritical Configuration Datamentioning

confidence: 99%

Evaluation of the Start-Up Core Physics Tests at Japan's High Temperature Engineering Test Reactor (Fully-Loaded Core)

Bess¹,

Fujimoto²,

Dolphin³

et al. 2010

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“…In the compositions used in the evaluation models, the natural-boron content is adjusted to include only the primary absorber 10 B, according to the isotopic abundance of 19.9 at.%.…”

Section: Evaluation Of Critical and / Or Subcritical Configuration Datamentioning

confidence: 99%

Evaluation of the Start-Up Core Physics Tests at Japan's High Temperature Engineering Test Reactor (Fully-Loaded Core)

Bess¹,

Fujimoto²,

Dolphin³

et al. 2010

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“…In a nuclear power plant, the pressure boundary formed by the containment body and numerous perforated equipment, components and pipes that penetrate the body is the third and last barrier of a nuclear power plant (Sakaba et al, 2004). It is responsible for the important function of preventing radioactive materials from leaking into the external environment.…”

Section: Introductionmentioning

confidence: 99%

A Method of Containment Leakage Rate Estimation Based on Convolution Neural Network

et al. 2021

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As the nuclear power plant containment is the third barrier to nuclear safety, real-time monitoring of containment leakage rate is very important in addition to the overall leakage test before an operation. At present, most of the containment leakage rate monitoring systems calculate the standard volume of moist air in the containment through monitoring parameters and calculate the daily leakage rate by the least square method. This method requires several days of data accumulation to accurately calculate. In this article, a new leakage rate modeling technique is proposed using a convolutional neural network based on data of the monitoring system. Use the daily monitoring parameters of nuclear power plants to construct inputs of the model and train the convolutional neural network with daily leakage rates as labels. This model makes use of the powerful nonlinear fitting ability of the convolutional neural network. It can use 1-day data to accurately calculate the containment leakage rate during the reactor start-up phase and can timely determine whether the containment leak has occurred during the start-up phase and deal with it in time, to ensure the integrity of the third barrier.

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“…The high temperature engineering test reactor (HTTR) employs a leak-tight containment whose leakage rate is designed to be lower than 0.1%/day in order to limit the total amount of air ingress (Sakaba et al, 2004). Takeda revealed that an injection of helium into lower part of the reactor is effective to prevent the onset of natural circulation of air in the reactor (Takeda, 2004).…”

Section: Introductionmentioning

confidence: 99%

Design approach for mitigation of air ingress in high temperature gas-cooled reactor

Satō

Ohashi

Nakagawa

2017

Mechanical Engineering Journal

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One important safety design consideration for high temperature gas-cooled reactor (HTGR) is air ingress following a rupture of the reactor pressure boundary such as primary piping. The air intrusion to the reactor core held at high temperature through the break will results in significant oxidation of graphite components and fuels. Such oxidation may leads to the weakening of core support structures as well as fuel element damage and subsequent fission product release. This paper intends to propose a practical solution to protect the reactor from severe oxidation against air ingress accidents without reliance on subsystems. Firstly, a change is made to the center reflector structure to minimize temperature difference during the accident condition in order to reduce buoyancy-driven natural circulation in the reactor. Secondly, a modified structure of the upper reflector is suggested to prevent massive air ingress against a rupture in standpipes. As a preliminary study, a numerical analysis is performed for a typical prismatic-type HTGR to study the effectiveness of the proposed design concept using simplified lumped element models. The analysis considers internal decay heat generation and transient heat conduction from inner to outer regions at the reactor core, cooling of vessel outer surface by radiation and natural convection, and natural circulation flow in reactor. The results showed that amount of air ingress into the reactor can be significantly reduced with practical changes to local structure in the reactor.

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Leak-tightness characteristics concerning the containment structures of the HTTR

Cited by 8 publications

References 0 publications

Evaluation of the Start-Up Core Physics Tests at Japan's High Temperature Engineering Test Reactor (Fully-Loaded Core)

Evaluation of the Start-Up Core Physics Tests at Japan's High Temperature Engineering Test Reactor (Fully-Loaded Core)

A Method of Containment Leakage Rate Estimation Based on Convolution Neural Network

Design approach for mitigation of air ingress in high temperature gas-cooled reactor

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