著者
古野 朗子 茅野 政道 山澤 弘実
出版者
一般社団法人 日本原子力学会
雑誌
日本原子力学会和文論文誌 (ISSN:13472879)
巻号頁・発行日
vol.5, no.3, pp.229-240, 2006-09-25 (Released:2010-01-21)
被引用数
7 or 0

This paper describes a method of estimating source term, i.e., location, period and amount of atmospheric release of radioactive material in real-time during nuclear emergency. This method consists of: (1) trial simulations of atmospheric dispersions on the possible combinations of these parameters and (2) statistical comparison of model predictions with offsite measurements of air concentrations of radionuclides and/or air dose rates from monitoring stations, to find a set of release condition providing model prediction that fits best to the measurement. A parallel execution method for efficiently processing many possible initial conditions is also developed. The performance of this method is favorably evaluated by a verification study using the dataset from European Tracer Experiment.
著者
藤高 和信
出版者
一般社団法人 日本原子力学会
雑誌
日本原子力学会誌 (ISSN:00047120)
巻号頁・発行日
vol.35, no.10, pp.880-884, 1993-10-30 (Released:2010-04-19)
被引用数
1 or 0
著者
西原 健司 山岸 功 安田 健一郎 石森 健一郎 田中 究 久野 剛彦 稲田 聡 後藤 雄一
出版者
一般社団法人 日本原子力学会
雑誌
日本原子力学会和文論文誌 (ISSN:13472879)
巻号頁・発行日
vol.advpub, pp.1202060058-1202060058, 2012 (Released:2012-02-08)
被引用数
14 or 0

After the severe accident in the Fukushima-1 nuclear power plant, a large amount of contaminated stagnant water has been produced in turbine buildings and surrounding areas. This rapid communication reports the calculation of the radionuclide inventory in the core, the collection of the measured inventory in the stagnant water, and the estimation of the radionuclide release ratios from the core to the stagnant water. The present evaluation is based on data obtained before June 3, 2011. It was revealed that the release ratios of tritium, iodine and cesium were several tens of percent, while those of strontium and barium were smaller by one or two orders of magnitude. These release ratios of the Fukushima accident were equivalent to those of the TMI-2 accident.
著者
西原 健司 山岸 功 安田 健一郎 石森 健一郎 田中 究 久野 剛彦 稲田 聡 後藤 雄一
出版者
一般社団法人 日本原子力学会
雑誌
日本原子力学会和文論文誌 (ISSN:13472879)
巻号頁・発行日
vol.11, no.1, pp.13-19, 2012 (Released:2012-02-15)
被引用数
14 or 0

After the severe accident in the Fukushima-1 nuclear power plant, a large amount of contaminated stagnant water has been produced in turbine buildings and surrounding areas. This rapid communication reports the calculation of the radionuclide inventory in the core, the collection of the measured inventory in the stagnant water, and the estimation of the radionuclide release ratios from the core to the stagnant water. The present evaluation is based on data obtained before June 3, 2011. It was revealed that the release ratios of tritium, iodine and cesium were several tens of percent, while those of strontium and barium were smaller by one or two orders of magnitude. These release ratios of the Fukushima accident were equivalent to those of the TMI-2 accident.
著者
斯波 正誼 天野 文雄
出版者
一般社団法人 日本原子力学会
雑誌
日本原子力学会誌 (ISSN:00047120)
巻号頁・発行日
vol.23, no.10, pp.736-745, 1981-10-30 (Released:2009-04-21)

The report presents the summary of Stockholm Conference held on October 20-24, 1980 sponsored by IAEA, where current nuclear power plant safety issues were discussed.Some technical topics are reviewed that include (1) examining nuclear safety, (2) siting policy, (3) designing for safety, (4) operational safety, (5) emergency planning, and (6) risk assessment, small leak loss of coolant accidents.
著者
平山 英夫 松村 宏 波戸 芳仁 佐波 俊哉
出版者
一般社団法人 日本原子力学会
雑誌
日本原子力学会和文論文誌 (ISSN:13472879)
巻号頁・発行日
vol.14, no.1, pp.1-11, 2015 (Released:2015-02-15)
被引用数
2 or 0

Time histories of the I-131 concentration in air at monitoring posts in Fukushima prefecture in March 2011 were estimated using the pulse height distribution of a NaI(Tl) detector, which was opened to the public. Several corrections to the pulse height distribution were necessary owing to high count rates. The contribution to the count rates from I-131 accumulated around the monitoring post was estimated on the basis of the time history of the peak count rate by the method proposed by the authors. The concentrations of I-131 in air were converted from the peak count rates using the calculated response of the NaI(Tl) detector with egs5 for a model of a plume containing I-131 uniformly. The obtained time histories of the I-131 concentration in air at a fixed point in March 2011 were the first ones for Fukushima prefecture. The results at 3 monitoring posts, Naraha Town Shoukan, Hirono Town Futatunuma and Fukushima City Momijiyama, which can be analyzed during almost all of March, show that a plume including I-131 arrived after March 15. The results at other monitoring posts near Fukushima Daiichi Nuclear Power Station are used to characterize plume diffusion at the early period of the accident before March 15. The I-131 time-integrated concentrations in air at several monitoring posts were compared with those given in UNSCEAR 2013 ANNEX A, which were obtained using estimated time-dependent rates of release to the atmosphere. The agreement between the two results varies depending on the places compared, owing to the large uncertainties in the estimated release rate used in UNSCEAR. The results obtained in this study can be used to increase the accuracy of the time-dependent release rate estimation.
著者
小林 健介 堀井 英雄 石神 努 千葉 猛美
出版者
一般社団法人 日本原子力学会
雑誌
日本原子力学会誌 (ISSN:00047120)
巻号頁・発行日
vol.27, no.1, pp.56-65, 1985-01-30 (Released:2009-04-21)
被引用数
1 or 0

A sensitivity analysis of thermal hydraulic response in containment during a 'station blackout' (the loss of all AC power) accident at Browns Ferry unit one plant was performed with the computer code MARCH 1.0. In the analysis, the plant station batteries were assumed to be available for 4h after the initiation of the accident. The thermal hydraulic response in the containment was calculated by varying several input data for MARCH 1.0 independently and the deviation among calculated results were investigated.The sensitivity analysis showed that (a) the containment would fail due to the overtemperature without any operator actions for plant recovery, which would be strongly dependent on the model of the debris-concrete interaction and the input parameters for specifying the containment failure modes in MARCH 1.0, (b) a core melting temperature and an amount of water left in a primary system at the end of the meltdown were identified as important parameters which influenced the time of the containment failure, and (c) experimental works regarding the parameters mentioned above could be recommended.
著者
水田 浩
出版者
一般社団法人 日本原子力学会
雑誌
日本原子力学会誌 (ISSN:00047120)
巻号頁・発行日
vol.16, no.5, pp.241-246, 1974-05-30 (Released:2009-04-21)

The most important safety problem concerning the LMFBR is related to core component damage caused by molten fuel coolant interaction. This problem has been reviewed under the items of out-of-pile test, in-pile test and analytical models. The elements of the physical geometry relevant to the out-of-pile test are shocktube, tank, jet injection, mixing and fuel pin. The major difficulty is to melt the large amount required of fuel (10kg). The in-pile test facilities operative today are TREAT, ETR, CABRI and HFR. Almost all the analytical models are based on the Cho-Wright model.
著者
阿部 清治 西 誠 渡辺 憲夫 工藤 和夫
出版者
一般社団法人 日本原子力学会
雑誌
日本原子力学会誌 (ISSN:00047120)
巻号頁・発行日
vol.27, no.11, pp.1035-1046, 1985-11-30 (Released:2009-04-21)
被引用数
1 or 0

THALES is a computer code system for the thermal-hydraulic analysis of the core meltdown accident which is the risk-dominant accident of LWR's. Its first version was developed for the PWR analysis, which uses THALES-P for primary system thermal-hydraulics, THALES-M for core heatup and meltdown, and THALES-CV for containment temperature and pressure response. Several program libraries were also developed not only for THALES but for general usage.A new analysis technique of hydraulics in the primary cooling system was developed and used in THALES-P with aiming at accurate estimation of water level in water-steam mixture and shorter computer time, which are necessary for the core meltdown analysis.This report describes the outlines of the THALES code system, as well as the mathematical modeling and sample run results of the above-mentioned codes. Further are discussed the importance of the mixture levels and the necessity of the core slumping models.
著者
石神 努 小林 健介
出版者
一般社団法人 日本原子力学会
雑誌
日本原子力学会誌 (ISSN:00047120)
巻号頁・発行日
vol.35, no.6, pp.549-560, 1993-06-30 (Released:2010-04-19)
被引用数
1 or 0

As a part of the preparation of the database of calculated results on severe accident sequences for emergency preparedness at nuclear power plants, steam generator tube rupture initiated severe accident sequences at a reference two-loop PWR plant have been analyzed using the THALES/ART computer code. Estimation were made of the times of key events such as core uncovery, core melt and reactor vessel melt-through, and an amount of fission products released to the environment. The effects of recovery action on core integrity and the amount of environmental fission products released were studied with regard to the discussion on mitigation of or recovery from the accident by the feed and/or bleed operation in the primary and/or the secondary system. The analysis showed that (1) the ECCS has adequate capability of maintaining core integrity, and (2) the bleed operation in the primary system is effective to suppress the environmental fission products released even if the ECCS did not function.
著者
平山 英夫 近藤 健次郎 海野 泰裕 松村 宏 岩瀬 広 柚木 彰 佐々木 慎一
出版者
一般社団法人 日本原子力学会
雑誌
日本原子力学会和文論文誌 (ISSN:13472879)
巻号頁・発行日
(Released:2015-06-30)

A rapid and simple method to measure the concentration of 90Sr in water by measuring β-rays from 90Y was presented. Under the situation that 90Sr/90Y, 134Cs and 137Cs are the main radionuclides included in the water sample, only β-rays from 90Y can transmit through 1.5-mm-thick polyethylene. From this fact, it is possible to measure β-rays from 90Y using a β-ray detector, such as the GM-counter, set beneath the 1.5-mm-thick bottom of the water bottle containing the sample with 90Sr/90Y. The acrylic resin collimator having 0 cm, 1.00 cm, 1.50 cm or 3.00 cm diameter was made to detect β-rays at the fixed region of the GM-counter used. Contributions from bremsstrahlung produced by β-rays and γ-rays from radionuclides such as 134Cs and 137Cs/137mBa are removed by subtracting the count rate measured with a 1.00 cm acrylic resin collimator without a hole as the background count rate. The developed method was studied using the bottle routinely used at the Fukushima Daiichi Nuclear Power Station. It was confirmed that the developed method can be applied to measure the 90Sr concentration in water to the order of several Bq/cm3 if 134Cs and 137Cs concentrations are less than or equal to the 90Sr/90Y concentration.
著者
坂本 文徳 大貫 敏彦 香西 直文 五十嵐 翔祐 山崎 信哉 吉田 善行 田中 俊一
出版者
一般社団法人 日本原子力学会
雑誌
日本原子力学会和文論文誌 (ISSN:13472879)
巻号頁・発行日
vol.11, no.1, pp.1-7, 2012 (Released:2012-02-15)
被引用数
4 or 0

The environmental behavior of radioactive Cs in the fallout from the accident of the Fukushima Daiichi Nuclear Power Plant has been studied by measuring its spatial distribution on/in trees, plants, and surface soil beneath the plants using autoradiography analysis. The results of autoradiography analysis showed that radioactive Cs was distributed on the branches and leaves of trees that were present during the accident and that only a small fraction of radioactive Cs was transported to new branches and leaves grown after the accident. Radioactive Cs was present on the grass and rice stubble on the soils, but not in the soils beneath the grass and rice stubble, indicating that the radioactive Cs was deposited on the grass and the rice plant. In addition, the ratio of the radioactive Cs that penetrated into the soil layer by weathering was very small two months after the accident. These results indicate that trees and other plants are the reservoir of the fallout Cs and function to retard the fallout Cs migration with rain water.
著者
近藤 健次郎 平山 英夫 平 雅文 松村 宏 岩瀬 広 佐々木 慎一
出版者
一般社団法人 日本原子力学会
雑誌
日本原子力学会和文論文誌 (ISSN:13472879)
巻号頁・発行日
(Released:2015-06-30)

Strontium-90/Y-90 are major radionuclides observed in the water samples tested recently at the site of the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company. A simple method of evaluating Sr-90 concentration in these water samples by measuring β rays from Y-90 with a GM-detector setup was developed. By applying the precipitation method, Sr-90 and Y-90 were separated and quantitatively collected with a filter. β rays from Y-90 in the filter were measured two times at appropriate intervals by inserting a polyethylene plate of 2 mm thickness as a β-ray absorber. The contribution of γ rays from Cs-134 and Cs-137 to the Y-90 count rates was quantitatively evaluated using a 10-mm-thick acrylic resin plate. From the parent-daughter relationship between Sr-90 and Y-90, the Sr-90 concentration was evaluated using the conversion coefficient of Y-90 count rate (cps) to Sr-90 concentration (Bq/cm3). It was verified that Sr-90 concentration of below 0.01 Bq/cm3 in water samples can be correctly measured by this simple method.