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Integration of pool scrubbing research to enhance source-term calculations (IPRESCA) project

Gupta, S.*; Herranz, L. E.*; Lebel, L. S.*; Sonnenkalb, M.*; Pellegrini, M.*; Marchetto, C.*; 丸山 結; Dehbi, A.*; Suckow, D.*; K$"a$rkel$"a$, T.*

Proceedings of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) (Internet), 16 Pages, 2022/03

Pool scrubbing is a major topic in water cooled nuclear reactor technology as it is one of the means for mitigating the source-term to the environment during a severe accident. Pool scrubbing phenomena include coupled interactions between bubble hydrodynamics, aerosols and gaseous radionuclides retention mechanisms under a broad range of thermal-hydraulic conditions as per accident scenarios. Modeling pool scrubbing in some relevant accident scenarios has shown to be affected by substantial uncertainties. In this context, IPRESCA (Integration of Pool scrubbing Research to Enhance Source-term CAlculations) project aims to promote a better integration of international research activities related to pool scrubbing by providing support in experimental research to broaden the current knowledge and database, and by supporting analytical research to facilitate systematic validation and model enhancement of the existing pool scrubbing codes. The project consortium includes more than 30 organisations from 15 countries involving research institutes, universities, TSOs, and industry. For IPRESCA activities, partners join the project with in-kind contributions. IPRESCA operates under NUGENIA Technical Area 2/SARNET (Severe Accident) - Sub Technical Area 2.4 (Source-term). The present paper provides an introduction and overview of the IPRESCA project, including its objectives, organizational structure and the main outcomes of completed activities. Furthermore, key activities currently ongoing or planned in the project framework are also discussed.


Some characteristics of gas-liquid two-phase flow in vertical large-diameter channels

Shen, X.*; Schlegel, J. P.*; 日引 俊*; 中村 秀夫

Nuclear Engineering and Design, 333, p.87 - 98, 2018/07

 被引用回数:5 パーセンタイル:30.29(Nuclear Science & Technology)

Two phase flows in large-diameter channels are important to efficiently and safely transfer mass and energy in a wide variety of applications including nuclear power plants. Two-phase flows in vertical large-diameter channels, however, show much more complex multi-dimensional nature than those in small diameter channels. Various constitutive equations are required to mathematically close the model to predict two-phase flows with two-fluid model. Validations of the constitutive equations require extensive experiment effort. This paper summarizes the recent experimental studies on two-phase flows in vertical large-diameter channels, which includes measuring technique and available databases. Then, a comprehensive review of constitutive equations is provided covering flow regime transition criteria, drift-flux correlations, interfacial area concentration correlations and one- and two-group interfacial area transport equation(s), with discussions on typical characteristics of large-diameter channel flows. Recent 1D numerical simulations of large-diameter channel flows is reviewed too. Finally, future research directions are suggested.


I-A. Models for atmospheric releases: I-A.1. Models used by JAERI, Japan

天野 光; 安藤 麻里子; 高橋 知之*

IAEA-BIOMASS-3, p.163 - 164, 2003/03



OSCAAR development and applications

本間 俊充

Proceedings of 4th International MACCS Users Group Meeting, p.57 - 66, 2002/10



Validation and sensitivity analysis of a new atmosphere-soil-vegetation model

永井 晴康

Journal of Applied Meteorology, 41(2), p.160 - 176, 2002/02



OSCAAR calculations for the Iput dose reconstruction scenario of BIOMASS theme 2

本間 俊充; 松永 武

JAERI-Research 2000-059, 63 Pages, 2001/01




OSCAAR calculations for the Hanford dose reconstruction scenario of BIOMASS theme 2

本間 俊充; 井上 佳久*; 富田 賢一*

JAERI-Research 2000-049, 101 Pages, 2000/10




A Database on tritium behavior in the chronic HT release experiment, 1; Meteorological data and tritium concentrations in air and soil

野口 宏; 横山 須美; 福谷 哲*; 木内 伸幸; 村田 幹生; 天野 光; 安藤 麻里子

JAERI-Data/Code 99-022, 125 Pages, 1999/03




トリチウムの影響と安全管理,IV-5; 線量評価モデルとパラメータ

野口 宏; 横山 須美

日本原子力学会誌, 39(11), p.931 - 933, 1997/00



Methodology of safety assessment for radioactive waste disposal

松鶴 秀夫; 木村 英雄

3rd Int. Symp. on Advanced Nuclear Energy Research; Global Environment and Nuclear Energy, 13 Pages, 1991/00




外川 織彦

保健物理, 24, p.166 - 169, 1989/00




林 伸彦; Garcia, J.*; 本多 充; 清水 勝宏; 星野 一生; 井手 俊介; Giruzzi, G.*; 坂本 宜照; 鈴木 隆博; 浦野 創

no journal, , 

Development of plasma operation scenarios in JT-60SA has been progressing by using integrated modeling codes. Anomalous heat transport model, which are one of major uncertainties in the prediction, have been validated for ITB plasmas with full current drive (CD) condition in JT-60U and JET, and integrated codes TOPICS and CRONOS equipped with the models are used for the model verification. It is found that CDBM model predicts temperatures close to those in experiments or underestimates them, and thus can be used for the conservative prediction. By using TOPICS with CDBM model, JT-60SA ITB plasmas with high $$beta_N$$ and full CD condition have been predicted consistently with Ar seeding to reduce the heat load on divertor plates below 10 MW/m$$^2$$. In the prediction, TOPICS is coupled with impurity transport code IMPACT to examine the Ar core accumulation for the influx to the core and the separatrix density evaluated by integrated divertor code SONIC. The Ar accumulation is found to be so mild that the performance can be recovered by additional heating. Due to the strong dependence of accumulation on the pedestal density gradient, the high separatrix density is important for low accumulation as well as low divertor heat load.

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