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Journal Articles

Temporal decrease in air dose rate in the sub-urban area affected by the Fukushima Dai-ichi Nuclear Power Plant accident during four years after decontamination works

Nakama, Shigeo; Yoshimura, Kazuya; Fujiwara, Kenso; Ishikawa, Hiroyasu; Iijima, Kazuki

Journal of Environmental Radioactivity, 208-209, p.106013_1 - 106013_8, 2019/11

 Times Cited Count:9 Percentile:35.3(Environmental Sciences)

Trends of air dose rate decrease after decontamination works and factors which affect them constitute essential information for radiation protection, such as prediction of external exposure to the public and implementation of measures to reduce such exposure. This study investigated the decrease of air dose rate (ambient dose rate at 1 m above the ground) at 163 points across sub-urban areas in the evacuation zone around the Fukushima Dai-ichi Nuclear Power Plant over the period of four years following the decontamination works carried out in November 2012. The air dose rate on the asphalt pavement decreased faster than on soil surfaces. In addition, air dose rates near the forest decreased at a slower pace than in open fields. These results suggest that the air dose rate in urbanized areas can decrease faster than in other types of land, even after decontamination. Based on comparisons with decrease rates obtained in other studies, the air dose rate tends to decrease faster outside the evacuation zone than inside it. The decrease in air dose rate after decontamination was slower than before decontamination. The contribution of the weathering effect and human activity was estimated to be about 80% and 20% of the ecological decrease rate, respectively.

Journal Articles

Decrease in air dose rate after decontamination relating to difference in the ground surface properties

Nakama, Shigeo; Yoshimura, Kazuya; Fujiwara, Kenso; Ishikawa, Hiroyasu; Iijima, Kazuki

KEK Proceedings 2018-7, p.154 - 158, 2018/11

Decrease in air dose rate in decontaminated area is essential information to estimate external exposure and to facilitate return of local residents, but the factors to control the decrease rate have not been cleared wholly. To clarify the effect of ground surface type (i.e. paved and soil surfaces) on the decrease in air dose rate at 1 m above the ground, surface dose rate at 1 cm above the ground and the air dose rate were monitored for four years since decontamination in 2011, and their decrease rates were compared relating to the ground surface type. Decrease in the air dose rate and the surface dose rate on the asphalt pavement showed faster rates than those on the soil surface. Ratio of decrease in the air dose rate and surface dose rate (decrease rate ratio) was distributed between 0.8 and 1.2 on open place not affected by surrounding environment. Therefore, decrease in the air dose rate was in agreement with the decrease of the surface dose rate, which is greatly affected by the ground surface. It became clear that the decrease rate constant of the air dose rate differs depending on the difference in the ground surface. Furthermore, it was also confirmed that the local soil erosion and sedimentation of the ground surface does not affect the decrease rate of the air dose rate.

Journal Articles

Conceptual design study for the demonstration reactor of JSFR, 5; Reactor cooling system design

Kisohara, Naoyuki; Ishikawa, Hiroyasu; Futagami, Satoshi; Xu, Y.*; Shimoji, Kuniyuki*; Kawamura, Masaya*

Proceedings of 19th International Conference on Nuclear Engineering (ICONE-19) (CD-ROM), 9 Pages, 2011/10

The cooling system of the JSFR adopts an integrated primary sodium pump/intermediate heat exchanger (IHX), dual structure straight tube steam generator (SG) and short elbow sodium piping layout. Since, however, this is the first experience applying these technologies to SFRs in Japan, design approaches have been evaluated and R&D has been undertaken. This paper addresses the design study of the cooling system of the demonstration reactor JSFR in terms of thermal-hydraulic and structural integrity. Recent studies have shown that these new technologies have potential to be applied to the JSFR.

Journal Articles

Experimental investigation of reaction behavior between carbon dioxide and liquid sodium

Miyahara, Shinya; Ishikawa, Hiroyasu; Yoshizawa, Yoshio*

Nuclear Engineering and Design, 241(5), p.1319 - 1328, 2011/05

 Times Cited Count:13 Percentile:69.42(Nuclear Science & Technology)

Reaction behavior of carbon dioxide (CO$$_{2}$$) with a liquid sodium pool was experimentally investigated to understand the consequences of boundary tube failure in a sodium-CO$$_{2}$$ heat exchanger (HX). In this study, two kinds of experiments, namely fundamental experiment and demonstration experiment which simulate the incident of CO$$_{2}$$ leakage in HX, were carried out to investigate the reaction behavior. From these experiments, it became clear that the exothermic reaction occurred above a threshold temperature, and useful and indispensable information such as the resulting temperature and pressure rise and the behavior of solid reaction products in the pool was obtained to evaluate the consequences of boundary tube failure incident in the sodium- CO$$_{2}$$ heat exchanger.

Journal Articles

Reaction behavior of carbon dioxide with liquid sodium pool

Miyahara, Shinya; Ishikawa, Hiroyasu; Yoshizawa, Yoshio*

Proceedings of 17th International Conference on Nuclear Engineering (ICONE-17) (CD-ROM), 8 Pages, 2009/06

Reaction behavior of carbon dioxide (CO$$_{2}$$) with a liquid sodium pool was experimentally investigated to understand the consequences of boundary tube failure in a sodium-CO$$_{2}$$ heat exchanger. In this study, two kinds of experiments were carried out to investigate the reaction behavior. In one experiment, about 1-5 g of liquid sodium pool were poured into flowing CO$$_{2}$$ to obtain the information mainly about the thermo-chemical conditions to initiate the reaction and the chemical constituents of reaction products. During the experiment, visual observation was made using video-camera and the temperature change of the sodium pool and near the surface was measured by thermocouples. In the other experiment, CO$$_{2}$$ was injected into about 200 g of liquid sodium pool to simulate the boundary failure in the sodium-CO$$_{2}$$ heat exchanger. The temperature change of sodium pool and the cover gas was measured by thermocouples during the experiment. From these experiments, it became clear that the exothermic reaction occurred above a threshold temperature, and useful and indispensable information such as the resulting temperature and pressure rise and the behavior of solid reaction products in the pool was obtained to evaluate the consequences of boundary tube failure incident in a sodium-CO$$_{2}$$ heat exchanger.

Journal Articles

Experimental study of sodium/carbon dioxide reaction

Ishikawa, Hiroyasu; Miyahara, Shinya; Yoshizawa, Yoshio*

Nihon Genshiryoku Gakkai Wabun Rombunshi, 7(4), p.452 - 461, 2008/12

Supercritical CO$$_{2}$$ is being investigated as a material for a secondary cooling system of Na-cooled fast reactor in to avoid Na/water reaction. In this type of reactor, however, it is necessary to consider the consequences of Na/CO$$_{2}$$ reaction, which might occur in the case of tube rupture in a heat exchanger between primary and secondary systems. Experiments were carried out with test equipment for the Na/CO$$_{2}$$ reaction, which can handle 1-5 g order of Na. The solid products of the Na/CO$$_{2}$$ reaction sampled from the equipment were analyzed by XRD and chemical analysis. From these experimental results, we proved that the reaction proceeded between liquid Na and CO$$_{2}$$. The Na/CO$$_{2}$$ reaction stopped only the pool surface reaction with a small quantity of aerosol emission when the temperature was lower than 570$$^{circ}$$C. On the other hand, the reaction continuously proceeded with on orange-colored flame and aerosol release when the temperature was higher than 580$$^{circ}$$C.

Journal Articles

Experimental Study of Sodium - Carbon Dioxide Reaction

Ishikawa, Hiroyasu; Miyahara, Shinya; Yoshizawa, Yoshio*

Proceedings of 2005 International Congress on Advances in Nuclear Power Plants (ICAPP '05) (CD-ROM), P. 5688, 2005/05

Focusing on the cover layer materials (as the Radon Barrier Materials), which could have the effect to restrain the radon from scattering into the air and the effect of the radiation shielding, we produced the radon barrier materials with crude bentonite on an experimental basis, using the rotary type comprehensive unit for grinding and mixing, through which we carried out the evaluation of the characteristics thereof.

JAEA Reports

Falling sodium droplet experiment (FD-3)

Doda, Norihiro; Ishikawa, Hiroyasu; Ohno, Shuji; Miyahara, Shinya

JNC TN9400 2005-048, 52 Pages, 2005/04

JNC-TN9400-2005-048.pdf:9.54MB

The burning behavior of a single sodium droplet has been studied for understanding of spray combustion which is one of the combustion forms in sodium leakage. This study serves as the basis of the mechanistic sodium fire analysis method. A burning experiment with initial droplet size of 3.34mm and 5.85mm different from FD-2 experiment condition (4.75mm), an inert gas condition experiment and a polypropylene sphere experiment were performed to investigate the relation between initial droplet size and burnt mass, and the effect of burning phenomena on the droplet motion. (1)Drag coefficient of a burning sodiuum droplet is 1.4$$sim$$2.2 times greater than that of a solid sphere of the same size. (2)The increase in drag force of a burning sodium droplet is mainly due to the increase in gaseous viscosity around the droplet with heat of combustion. Sodium droplet has the ellipsoidal shape with aspect ratio 0.89 when falling by about 8 meters, but the effect of droplet deformation is negligible small. In addition, evaporation and buoyancy have also little effect on the increase in drag force. (3)The burning of sodium droplet follows the D$$^{2}$$-law when the initial droplet diameter changes. In the calculation which assumes that the sodium combustion quantity agrees with the measurement and that combustion of sodium droplet obeys that law, the Na$$_{2}$$O ratio of reaction products becomes 0.51-0.75.

Journal Articles

Sodium fire study in Japan Nuclear Cycle Development Institute (II)

Ishikawa, Hiroyasu; Doda, Norihiro; Miyahara, Shinya

Kasai, 55(1), p.50 - 60, 2005/00

This paper is a report of sodium fire study in Japan Nuclear Cycle Development Institute.

JAEA Reports

Conclusive Experimental Study of Prevention Measures Against Sodium Combustion Residuum Reignition; Run-F9-1, Run-F9-2

Ishikawa, Hiroyasu; Ohno, Shuji; Miyahara, Shinya

JNC TN9400 2004-038, 84 Pages, 2004/04

JNC-TN9400-2004-038.pdf:10.3MB

Nitrogen gas can be an extinguisher or a mitigating material in the case of sodium leak and fire accident in an air atmosphere, which may occur at a liquid metal cooled nuclear power plant. However, sodium combustion residuum sometimes reignites in the air atmosphere even at room temperature when it was produced by nitrogen gas injection to the burning sodium. Then, in this study we executed conclusive experiments of prevention measures against sodium combustion residuum reignition by a mixture of carbon-dioxide (C0 sub2) gas, humidity and nitrogen gas. The experiments were carried out with the FRAT-1 test equipment; the humidity conditions were changed in air which were used to sodium combustion atmosphere and exposure air for confirmation of prevented combustion residue reignition. First of all, the sodium of about 2.5kg was leaked in air atmosphere, and next, the sodium combustion was stopped by nitrogen gas injection. Next, the combustion residuum was cooled in the nitrogen atmosphere, and then the combustion residuum was exposed to atmosphere of carbon-dioxide (4%); humidity (6000vppm); oxygen (3%)-nitrogen (based gas) mixture. It was confirmed that the combustion residuum was not reignition even if exposed to the air atmosphere again at the end of experiment. We had confirmed that the prevention measures against sodium combustion residuum reignition to establish by this research were effective.

Journal Articles

Sodium Fire Study in Japan Nuclear Cycle Development Institute (I)

Ishikawa, H.; Ohno, Shuji; Miyahara, Shinya

Kasai, 54(6), 43-49 Pages, 2004/00

Focusing on the cover layer materials (as the Radon Barrier Materials), which could have the effect to restrain the radon from scattering into the air and the effect of the radiation shielding, we produced the radon barrier materials with crude bentonite on an experimental basis, using the rotary type comprehensive unit for grinding and mixing, through which we carried out the evaluation of the characteristics thereof.

JAEA Reports

Experimental study of prevention measures against sodium combustion residuum reignition

Ishikawa, Hiroyasu; Ohno, Shuji; Miyahara, Shinya

JNC TN9400 2002-081, 46 Pages, 2003/01

JNC-TN9400-2002-081.pdf:2.21MB

Nitrogen gas can be an extinguisher or a mitigating material in the case of sodium leak and fire accident in an air atmosphere, which may occur at a liquid metal cooled nuclear power plant. However sodium combustion residuum sometimes reignites in the air atmosphere even at room temperature when it was produced by nitrogen gas injection to the burning sodium. In this study we have been investigating the cause of reignition and prevention measures. Experiments were carried out with small type test equipment, which can handle 1g order sodium fire and extinguishment. Sodium combustion residua, which were made by our equipment and sampled, were analyzed by X-ray diffraction and chemical analysis. The chemical analysis of reignitable residua showed that the residuum contained metallic sodium of about 40wt-% (61 mol-%) to 60-wt % (76mol-%) and most of the rest was sodium-monoxide (Na$$_{2}$$O). Sodium-peroxide (Na$$_{2}$$O$$_{2}$$) was also included in less than 1wt-% of the residuum. Sodium or Na$$_{2}$$O cannot ignite by itself in the air atmosphere at room temperature in a few minutes. Therefore the reignition seems to be due to increase in the local temperature that is caused by oxidizing heat of Na and by adiabatic effect of Na$$_{2}$$O. It is important to deactivate this dispersed sodium on oxygen for prevention of the residuum reignition, hence it is considered as a rational measure to change the sodium to sodium-carbonate. Our experiments showed that the dispersed sodium on the exterior of residuum could be changed to carbonate by a mixture of carbon-dioxide (CO$$_{2}$$) gas (2 to 8vol-%), humidity (0.6 to 3vol-%) and nitrogen gas. The deactivated residuum did not reignite in the air atmosphere below 473K.

Journal Articles

None

Miyahara, Shinya; Ohno, Shuji; ; Doda, Norihiro

Nihon Nensho Gakkai-Shi, 45(133), 0 Pages, 2003/00

None

Journal Articles

Experimental Study of Prevention Measures against Sodium Combustion Residuum Reignition

Ishikawa, Hiroyasu; Ohno, Shuji; Miyahara, Shinya

Nihon Nensho Gakkai-Shi, 45(134), 248 Pages, 2003/00

Nitrogen gas can be an extinguisher or a mitigating in the case of sodium leak and fire accident in an air atmonphere, which may occur at a liquid metal cooled nuclear power plant. However sodium combustion residuum sometimes reignites in the air atmosphere even at room temperature when it was produced by nitrogen gas injection to the burning sodium. In this study we have been investigating the cause of reignition and prevention measures. Experiments were carried out with small type test equipment, which can handle 1g order sodium fire and extinguishment. Sodium combustion residua, which were made by our equipment and sampled, were analyzed by X-ray diffraction and chemical analyses. The chemical analysis of reignitable residua showed that the residuum contained metallic sodium of about 40Wt-%(61mol-%)to 60-wt %(76mol-%) and most of the rest was sodium-monoxide (Na2O).Sodium-peroxide (Na2O2) was also included in less than 1wt-% of the residuu. Sodium or Na2O cannot ignite by itself in the air atmosphere at room temperature in a few minutes. Therefore the reignition seems to be due to increase in the local temperature that is caused by oxidizing heat of Na and by adiabatic effect of Na2O. It is important to deactivate this dispersed sodium on oxygen for prevention of the residuum reigntion, hence it is considered as a rational measure to change the sodium to sodium-carbonate. Our experments showed that the dispersed sodium on the exterior of residuum could be changed to carbonate by a mixture by a mixture of carbon-dioxide(CO2) gas (2 to 8vol-%),humidity (0.6 to 3vol-%) and mitrogen gas. The deactivated residuum did not reignite in the air atmospherebe bwlow 473K.

JAEA Reports

Sodium pooI combustion Test (Run-F7-3 and Run-F8-1) to confirm the condition of floor liner's corrosion

; ; Ohno, Shuji;

JNC TN9400 2000-092, 247 Pages, 2000/08

JNC-TN9400-2000-092.pdf:20.29MB

Small-scale sodium pool combustion tests Run-F7-3 and Run-F8-1 were performed to investigate the corrosion of floor liner under high moisture condition. ln the both tests, which were performed using the 3m$$^{3}$$ FRAT-1 vessel at the SAPFIRE facility, the sodium of 507deg-C was leaked on the carbon steel catch pan about for 25 minutes with the flow rate of around 25 kg/h. The air in the vessel was ventilated with the flow rate of 5m$$^{3}$$/min containing the moisture of 25000-28000 vol.ppm. The duration of combustion was different in two tests by changing the starting time of argon gas injection into the vessel. As the results of post-test analysis such as observation of catch pan surface and chemical analysis of the deposits, it was confirmed that 'Na-Fe double oxidization type corrosion' was dominant in the both tests and that the catch pan and deposits were not under the condition leading to the occurrence of 'molten salt type corrosion.'

JAEA Reports

None

; Hayafune, Hiroki; ; ; ; Kawasaki, Nobuchika;

JNC TY9400 2000-024, 706 Pages, 2000/06

JNC-TY9400-2000-024.pdf:28.02MB

no abstracts in English

JAEA Reports

Conceptua1 design study on simplified and safer cooling systems for sodium cooled FBRs

Hayafune, Hiroki; Shimakawa, Yoshio; ; ; ;

JNC TN9400 2000-107, 156 Pages, 2000/06

JNC-TN9400-2000-107.pdf:5.98MB

The objective of this study is to create the FBR plant concepts increasing economy and safety for the Phase-I "Feasibility Studies on Commercialized Fast Reactor System". In this study, various concepts of simplified 2ry cooling system for sodium cooled FBRs are considered and evaluated from the view points of technological feasibility, economy, and safety. The concepts in the study are considered on the basis of the following points of view. (1)To simplify 2ry cooling system by moderating and localizing the sodium-water reaction in the steam generator of the FBRs. (2)To simplify 2ry coolig system by eliminatig the sodium-water reaction using integrated IHX-SG unit (3)To simplify 2ry cooling system by eliminating the sodium-water reaction using a power generating system other than the steam generator. As the result of the study, 12 concepts and 3 innovative concepts are proposed. The evaluation study for those concepts shows the following technical prospects. (1)2 concepts of integrated IHX-SG unit can eliminate the sodium-water reaction (a)Separated IHX and SG tubes unit usig Lead-Bismuth as the heat transfer medium (b)lntegrated IHX-SG unit using copper as the heat transfer medium (2)Cost reduction effect by simplified 2ry cooling system using integrated IHX-SG unit is estimated 0 to 5%. (3)A11 of the integrated IHX-SG unit concepts have more weight and larger size than an conventional steam generator unit. The weight of the unit during transporting and lifting would limit capacity of heat transfer system. These evaluation results will be compared with the results in JFY 2000 and used for the Phase-II study.

JAEA Reports

Studies on sodium cooled fast breeder reactor

Nibe, Nobuaki; Shimakawa, Yoshio; ; Hayafune, Hiroki; ; ;

JNC TN9400 2000-074, 388 Pages, 2000/06

JNC-TN9400-2000-074.pdf:13.32MB

Large sized sodium-cooled fast breeder reactors of large-size are being studied and have been operated in Japan and many countries. ln this feasibility study, evaluation was made on technical feasibinty for design concepts or 1 loop type and 3 pool types, specially from the viewpoint of improvement of economical competence. The design concepts include the ideas of cost reduction measures such as large-scaled components, reduction of loop number and integration of components on the basic of utilization of sodium characteristics. From the results of the evaluation, it may be possible for all the concepts to attain the economical target of 200 thousands yen per kilowatt, though further confirmation should be made for technical feasibility of those concepts. ln addition, the following items were listed up as further cost-reduction measures. (1)Higher temperature cooling system and steam cycle efficiency (2)Shortening of construction term (3)Reduction of safety systems by using measuring instruments with high performmce (4)Adoption of SG-ACS

JAEA Reports

Sodium combustion computer code ASSCOPS Version 2.1; User's manual

Ohno, Shuji; Matsuki, Takuo*; ; Miyake, Osamu

JNC TN9520 2000-001, 196 Pages, 2000/01

JNC-TN9520-2000-001.pdf:5.13MB

ASSCOPS (Analysis of Simultaneous Sodium Combustion in Pool and Spray) has been developed for analyses of thermal consequences of sodium leak and fire accidents in LMFBRs. This report presents a description of the computational models, input and output data as the user's manual of ASSCOPS version 2.1. ASSCOPS is an integrated computational code based on the sodium pool fire code SOFIRE II developed by the Atomics International Division of Rockwell International, and on the sodium spray fire code SPRAY developed by the Hanford Engineering Development Laboratory in the U.S. The users of ASSCOPS need to specify the sodium leak conditions (leak flow rate and temperature, etc.), the cell geometries (cell volume, surface area and thickness of structures, etc.), and the atmospheric initial conditions such as gas temperature, pressure, and composition. ASSCOPS calculates the time histories of atmospheric temperature, pressure and of structural temperature.

JAEA Reports

Experimental study of sodium reignition behavior

Ohno, Shuji; ; *; ;

JNC TN9400 99-081, 74 Pages, 1999/10

JNC-TN9400-99-081.pdf:1.82MB

Reaction residue of sodium combustion has possibility of reignition in an air atmosphere even at 50$$^{circ}$$C when the sodium pool fire was extinguished by nitrogen (N$$_{2}$$) gas. Thus we carried out an experimental study of this behavior for the purpose to clarify the cause of the reignition and to make a suggestion for a preventive measure. The sodium burning and extinguishing experiments were performed changing fraction of oxygen (O$$_{2}$$), carbon-dioxide (CO$$_{2}$$) and humidity in the atmosphere, using 1g sodium and a glass-made chamber of 70mm inner diameter and 300mm length. By the observation of phenomena, measurement of reignition temperature, and analyses of reaction residue, the following results and conclusions were obtained. (1)When the burning was distinguished by pure N$$_{2}$$ gas, reignition did not occur at 59$$^{circ}$$C. However, reignition occurred at 50$$^{circ}$$C when the distinguishing N$$_{2}$$ gas contained over 1% O$$_{2}$$. (2)Reignition temperature became higher by supplying humidity and CO$$_{2}$$ after cooling down the residue, even when the distinguishing N$$_{2}$$ gas contained O$$_{2}$$. (3)The reaction residue consisted mainly of Na$$_{2}$$O and Na, partly of NaOH, Na$$_{2}$$CO$$_{3}$$, and Na$$_{2}$$O$$_{2}$$ depending on the experimental condition. No peculiar compound was detected. The reignition might be attributed to the sharply projecting-shaped gray-white-colored reaction products which contains Na$$_{2}$$O.

39 (Records 1-20 displayed on this page)