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論文

Development of air cooling performance evaluation method for fuel debris on retrieval of Fukushima Daiichi NPS by dry method, 2; Outline of numerical method and preliminary analysis of free convection around fuel debris

山下 晋; 上澤 伸一郎; 吉田 啓之

Proceedings of 10th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-10) (USB Flash Drive), 7 Pages, 2016/11

福島第一原子力発電所廃止措置における燃料デブリ取り出し工法において、気中工法が検討されている。気中における燃料デブリの冷却能力の検討が、この工法実現のための重要な課題であるといえる。しかしながら、燃料デブリの形状や表面温度には大きな不確かさがあり、冷却能力を評価するには、それらの影響を含めて自然対流による冷却能力を評価する必要がある。そこで原子力機構では、JUPITERコードを使って、燃料デブリの自然対流による冷却能力を評価できる手法の開発を行っている。本報では、解析手法の概要と予備解析として実施した、模擬体系での自然対流による燃料デブリから気中への熱伝達の評価結果等について発表する。

論文

Development of air cooling performance evaluation method for fuel debris on retrieval of Fukushima Daiichi NPS by dry method, 3; Heat transfer and flow visualization experiment of free convection adjacent to upward facing horizontal surface

上澤 伸一郎; 柴田 光彦; 山下 晋; 吉田 啓之

Proceedings of 10th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-10) (USB Flash Drive), 7 Pages, 2016/11

A dry method for fuel debris retrieval is proposed for decommissioning of TEPCO's Fukushima Daiichi NPS. However, air cooling performance has not yet been strictly evaluated for the fuel debris. We have developed an evaluation method based on a numerical simulation code, JUPITER, to understand the cooling performance. Moreover, a heat transfer and flow visualization experiment in air is also conducted in order to validate the numerical analysis. In this paper, to decide measurement targets of the experiment, we roughly estimated the heat transfer of the fuel debris exposed to the air. The rough estimation indicated that the evaluation of the free convection and the radiation heat transfer were important to understand the heat transfer of the debris. Considering the estimations, a preliminary experiment for the free convection in air adjacent to upward-facing horizontal heat transfer surface was conducted to discuss applicability of the temperature measurement systems and the flow visualization systems to the experiment for the validation of the JUPITER. By the preliminary experiment, we confirmed that heat transfer temperature, air temperature and emissivity can be measured with thermocouples and the infrared camera. The applicability of a PIV to measure velocity fields of the free convection in air was also confirmed.

論文

Development of air cooling performance evaluation method for fuel debris on retrieval of Fukushima Daiichi NPS by dry method, 1; Outline of research project

吉田 啓之; 上澤 伸一郎; 山下 晋; 永瀬 文久

Proceedings of 10th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-10) (USB Flash Drive), 7 Pages, 2016/11

To perform the decommissioning of the TEPCO's Fukushima Daiichi Nuclear Power Station, it is considered that application of four methods (full submersion, submersion, partial submersion and dry methods) to perform fuel debris retrieval from the reactor pressure vessels and the primary containment vessels. In the dry method, the fuel debris is exposed in air, and neither cooling nor filling of water is involved. Therefore, by using this method, the stopping water leakage from the PCV is not necessary. However, evaluation of the cooling performance of air convection for fuel debris is required to perform this method. JAEA starts the research project to develop an evaluation method to estimate the air cooling performance for fuel debris. The evaluation method is developed based on the JUPITER, which has been originally developed to estimate the relocation behavior of melting fuel, in order to estimate the cooling performance by considering the melting fuel debris distribution as initial and boundary conditions. To develop and validate the simulation method for the air cooling of the fuel debris, experimental database is required. Then, a heat-transfer and flow visualization experiment of free and/or mixed convection adjacent to upward-facing horizontal surface is conducted in this research project.

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