著者

川村 慎一 奈良林 直

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.15, no.2, pp.84-96, 2016

被引用文献数

1

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Three nuclear reactors at Fukushima Daini Nuclear Power Station lost all their ultimate heat sinks owing to damage from the tsunami caused by the Great East Japan Earthquake on March 11, 2011. Water was injected into the reactors by alternate measures, damaged cooling systems were restored with promptly supplied substitute materials, and all the reactors were brought to a cold shutdown state within four days. Lessons learned from this experience were identified to improve emergency management, especially in the areas of strategic response planning, logistics, and functions supporting response activities continuing over a long period. It was found that continuous planning activities reflecting information from plant parameters and response action results were important, and that relevant functions in emergency response organizations should be integrated. Logistics were handled successfully but many difficulties were experienced. Therefore, their functions should be clearly established and improved by emergency response organizations. Supporting emergency responders in the aspects of their physical and mental conditions was important for sustaining continuous response. As a platform for improvement, the concept of the Incident Command System was applied for the first time to a nuclear emergency management system, with specific improvement ideas such as a phased approach in response planning and common operation pictures.

著者

竹上 弘彰 高松 邦吉 伊藤 主税 日野 竜太郎 鈴木 敬一 大沼 寛 奥村 忠彦

出版者

Atomic Energy Society of Japan

雑誌

日本原子力学会和文論文誌 (ISSN:13472879)

巻号頁・発行日

vol.13, no.1, pp.7-16, 2014

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One of the important problems in the control of the Fukushima Daiichi Nuclear Power Plant is the removal of fuel debris. As preparation, a nondestructive inspection method for identifying the position of fuel debris is required. Therefore, we focused on a nondestructive inspection method using cosmic-ray muons, which is utilized for ground investigation. In this study, the applicability of this method for internal visualization of the reactor was confirmed by a preliminary test of the internal visualization of the High-Temperature Engineering Test Reactor (HTTR) of Japan Atomic Energy Agency. By using cosmic-ray muons, main components in the HTTR reactor, such as concrete walls and the reactor core, can be observed from the outside of the containment vessel of the HTTR. From the results of the preliminary examination, it appears that the inspection method with muons is promising for searching for fuel debris in a reactor. Based on the results, we also proposed some improvements of this system for its application to inspection at the Fukushima Daiichi Nuclear Power Station.<br>

著者

竹上 弘彰 高松 邦吉 伊藤 主税 日野 竜太郎 鈴木 敬一 大沼 寛 奥村 忠彦

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.13, no.1, pp.7-16, 2014 (Released:2014-02-15)

参考文献数

10

被引用文献数

1

---

One of the important problems in the control of the Fukushima Daiichi Nuclear Power Plant is the removal of fuel debris. As preparation, a nondestructive inspection method for identifying the position of fuel debris is required. Therefore, we focused on a nondestructive inspection method using cosmic-ray muons, which is utilized for ground investigation. In this study, the applicability of this method for internal visualization of the reactor was confirmed by a preliminary test of the internal visualization of the High-Temperature Engineering Test Reactor (HTTR) of Japan Atomic Energy Agency. By using cosmic-ray muons, main components in the HTTR reactor, such as concrete walls and the reactor core, can be observed from the outside of the containment vessel of the HTTR. From the results of the preliminary examination, it appears that the inspection method with muons is promising for searching for fuel debris in a reactor. Based on the results, we also proposed some improvements of this system for its application to inspection at the Fukushima Daiichi Nuclear Power Station.

著者

高橋 啓三

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.2, pp.152-165, 2006-06-25 (Released:2010-01-21)

参考文献数

22

被引用文献数

1 2

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As for the nuclear fuel reprocessing of the spent fuel, although there was argument of pros and cons, it was decided to start Rokkasho reprocessing project further at the Japan Atomic Energy Commission of "Long-Term Program forResearch, Development and Utilization of Nuclear Energy" in year 2004. The operation of Tokai Reprocessing is goingsteadily to reprocess spent fuel more than 1, 100 tons.In this paper, history, present status and future of reprocessing technology is discussed focusing from military Puproduction, Magnox fuel reprocessing to oxide fuel reprocessing. Amount of reprocessed fuel are estimated based on fueltype.Then, history of reprocessing, US, UK, France, Germany, Russian, Belgian and Japan is presented and compared ontechnology, national character, development organization, environmental protection, and high active waste vitrification.Technical requirements are increased from Pu production fuel, Magnox fuel and oxide fuel mainly because of higherburnup.Reprocessing technology is synthetic of engineering and accumulation of operational experience. The lessonslearned from the operational experience of the world will be helpful for establishment of nuclear fuel reprocessing technology in Japan.

著者

寺田 宏明 永井 晴康 古野 朗子 掛札 豊和 原山 卓也 茅野 政道

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.7, no.3, pp.257-267, 2008 (Released:2012-03-02)

参考文献数

19

被引用文献数

4 26

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The second version of WSPEEDI (WSPEEDI-II) is developed. It has functions to predict the radiological impact of nuclear accident abroad on Japan by quick calculations of air concentration, surface deposition, and radiological doses. WSPEEDI-II has the following new functions for better predictions and practical use: (1) high-performance prediction of atmospheric dispersion of radionuclides from local to regional ranges with appropriate resolutions by introducing a nonhydrostatic atmospheric dynamic model, (2) source term estimation by coupling calculation results and monitoring data for the case that no source information is available from abroad, (3) on-line prediction data exchanges with major emergency response systems in the United States and Europe having similar functions to WSPEEDI-II, (4) web-based graphical user interface system for easy operations of WSPEEDI-II, and (5) preset East-Asian database for quick start against a nuclear accident in Eastern Asia.   In this paper, we describe these new functions of WSPEEDI-II.

著者

芳原 新也 稲垣 昌代 小島 清 山西 弘城 若林 源一郎 杉山 亘 伊藤 哲夫

出版者

Atomic Energy Society of Japan

雑誌

日本原子力学会和文論文誌 (ISSN:13472879)

巻号頁・発行日

vol.10, no.3, pp.145-148, 2011 (Released:2011-07-29)

参考文献数

14

被引用文献数

5 4

---

Radioactive materials were released to the general environment due to the accident at the Fukushima Daiichi nuclear power station. The released radioactive materials fell and contaminated the land mainly in the Tohoku and Kanto areas of Japan. We surveyed the air dose rate in relation to the pave condition of the land, and investigated the contamination level in some nonpaved areas at the center of Fukushima City, Koriyama City, and Nasushiobara City. From the survey results, the dose rates of the nonpaved areas were found to be higher than those of the paved areas, and the dose rates of the paved areas depend on the paving materials of the area. The contamination level of the nonpaved area in Nasushiobara City was below the regulation level of specific activities in a radiation-controlled area in Japan. However, the contamination levels in the nonpaved areas in Fukushima City and Koriyama City were above the regulation level.

著者

坂本 文徳 大貫 敏彦 香西 直文 山崎 信哉 吉田 善行 難波 謙二

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

pp.J13.002, (Released:2013-10-10)

参考文献数

20

被引用文献数

4 5

---

The local area distribution and relocation of radioactive cesium deposited in trees after the 2011 tsunami-related accident at the Fukushima Daiichi Nuclear Power Plant (FDNPP) have been studied by measuring the spatial distribution of cesium on/in trees by autoradiography analysis. Samples of trees were collected from places located between 4 and 55 km from FDNPP approximately 2, 8, 20, and 22 months after the accident. The autoradiography analyses of Cryptomeria japonica, Torreya nucifera, and Thujopsis dolabrata var. hondae samples collected approximately 2 and 8 months after the accident showed that radioactive Cs was mainly distributed as spots on the branches and leaves of the trees emerged before the accident, and was detected in negligible amounts in new branch and leaves that emerged after the accident. On the contrary, radioactive Cs was detected at the outermost tip of the branches in the trees collected 20 months after the accident. Morus alba samples collected 22 months after the accident contained radioactive Cs inside and outside their stems, even though no radioactive Cs was detected in their roots, strongly suggesting that a certain amount of radioactive Cs was translocated from the outside to the inside of stems. These results indicate that the distribution of radioactive Cs deposited on/in the trees gradually changes with time (scale: year).

著者

平山 英夫 佐波 俊哉 波戸 芳仁

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

pp.J12.043, (Released:2013-06-27)

参考文献数

4

被引用文献数

4 6

---

Gamma-ray pulse-height distributions from widely distributed Cs-134 and Cs-137 calculated using the EGS5 Monte Carlo code with the transformation of a system consisting of a plane isotropic source and a unit sphere detector into a system consisting of a point isotropic source and a plane detector were compared with measured ones. Results agree well in terms of both spectrum shape and absolute value. Spectra at a height of 1 m from widely distributed I-131, Cs-134 and Cs-137 were studied by EGS5 calculation. It was clarified that the contribution of scattered gamma rays is dominant within the total gamma-ray flux. The contributions of the scattered gamma rays to ambient dose equivalents and effective dose were also studied.

著者

渡辺 正 石垣 将宏 佐藤 聡 中村 秀夫

出版者

Atomic Energy Society of Japan

雑誌

日本原子力学会和文論文誌 (ISSN:13472879)

巻号頁・発行日

vol.10, no.4, pp.240-244, 2011 (Released:2011-11-30)

参考文献数

4

被引用文献数

2 2

---

The analysis of the long-term station blackout accident of BWR has been performed using the TRAC-BF1 code. The actuation of RCIC was assumed, and the results were compared with the data observed at the Fukushima Daiichi power plant unit 2 reactor. BWR-5 of 1,100 MW was analyzed, while the unit 2 reactor was BWR-4 of 780 MW. The reactor pressure and the core liquid level were, however, in good agreement with the observed data. It was confirmed that the quasi-steady state continued for a long time with the RCIC actuation. The timing of recovery action, which was composed of depressurization and coolant injection, necessary for the maximum clad temperature being less than 1,500 K was studied and compared with that of the unit 2 reactor.

著者

池田 佳隆 岡野 文範 逆井 章 花田 磨砂也 秋野 昇 市毛 尚志 神永 敦嗣 清野 公広 久保 博孝 小林 和容 笹島 唯之 助川 篤彦 千葉 真一 西山 友和 三代 康彦 柳生 純一 横倉 賢治 JT-60 チーム

出版者

Atomic Energy Society of Japan

雑誌

日本原子力学会和文論文誌 (ISSN:13472879)

巻号頁・発行日

vol.13, no.4, pp.167-178, 2014 (Released:2014-11-15)

参考文献数

14

---

The upgrade of JT-60U to the superconducting tokamak “JT-60SA” has been carried out as a combined project of JAEA's program for national use and the Satellite Tokamak Program in collaboration with EU and Japan fusion communities. The JT-60U torus was dismantled so as to install the new JT-60SA torus at the same position in the torus hall. JT-60U used deuterium for 18 years, so the neutron yield reached about 1.5×1020 (n) in total. The dismantling project of JT-60U was the first decommissioning experience of a fusion device with radioactivity in Japan. The project was intended to demonstrate decommissioning technologies and work activities, and to acquire experience and data on the technologies as well as to implement the dismantling project safely. Moreover, all disassembled components were stored with the data such as dose rate, weight and kind of material being recorded, so as to apply the clearance level regulation in the future. The lessons learned from the dismantling project indicated that the cutting technologies and storage management of disassembled components were the key factors in conducting the dismantling project efficiently. After completing the dismantling project, efforts have been made to analyze the data for characterizing disassembling activities, so as to contribute to the estimation of manpower needs and the radioactivity of the disassembled components from other fusion devices.

著者

坂場 成昭 大橋 弘史 佐藤 博之 原 輝夫 加藤 竜馬 國富 一彦

出版者

Atomic Energy Society of Japan

雑誌

日本原子力学会和文論文誌 (ISSN:13472879)

巻号頁・発行日

vol.7, no.3, pp.242-256, 2008 (Released:2012-03-02)

参考文献数

30

被引用文献数

6 6

---

Nuclear hydrogen production is necessary in an anticipated hydrogen society that demands a massive quantity of hydrogen without economic disadvantage. Japan Atomic Energy Agency (JAEA) has launched the conceptual design study of a hydrogen production system with a near-term plan to connect it to Japan's first high-temperature gas-cooled reactor HTTR. The candidate hydrogen production system is based on the thermochemical water-splitting iodine sulphur (IS) process. The heat of 10 MWth at approximately 900°C, which can be provided by the secondary helium from the intermediate heat exchanger of the HTTR, is the energy input to the hydrogen production system. In this paper, we describe the recent progresses made in the conceptual design of advanced process heat exchangers of the HTTR-IS hydrogen production system. A new concept of sulphuric acid decomposer is proposed. This involves the integration of three separate functions of sulphuric acid decomposer, sulphur trioxide decomposer, and process heat exchanger. A new mixer-settler type of Bunsen reactor is also designed. This integrates three separate functions of Bunsen reactor, phase separator, and pump. The new concepts are expected to result in improved economics through construction and operation cost reductions because the number of process equipment and complicated connections between the equipment has been substantially reduced.

著者

古谷 正裕 稲田 文夫

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会和文論文誌 (ISSN:13472879)

巻号頁・発行日

vol.3, no.2, pp.141-150, 2004-06-25 (Released:2010-03-08)

参考文献数

13

---

Experiments were conducted to investigete two-phase flow stability of a natural circulation BWR due to flashing at low pressure. The facility used in the experiment was designed to have non-dimensional values which are nearly equal to those of typical natural circulation BWR. The observed instability is suggested to be the flashing induced density wave oscillations, since the oscillation period was nearly one and a half to two times the passing time in the chimney section, and correlated well with a single line regardless of system pressure, heat flux, and inlet subcooling. Stability maps were obtained in reference to the core inlet subcooling and the heat flux at the system pressures of 0.1, 0.2, 0.35, and 0.5MPa. The flow became stable below a certain heat flux regardless of the channel inlet subcooling. The stable region enlarged with increasing system pressure. According to the stability map, the stability margin becomes larger in a startup process of a reactor by pressurizing the reactor sufficiently before withdrawing control rods.

著者

皆月 功 溝上 頼賢

出版者

Atomic Energy Society of Japan

雑誌

日本原子力学会和文論文誌 (ISSN:13472879)

巻号頁・発行日

vol.6, no.3, pp.276-288, 2007 (Released:2012-03-07)

参考文献数

13

被引用文献数

2 2

---

The design studies on High Temperature Gas Cooled Reactor with Gas Turbine (HTGR-GT) have been performed, which were mainly promoted by Japan Atomic Energy Agency (JAEA) and supported by fabricators in Japan. HTGR-GT plant feature is almost determined by selection of power conversion system concepts. Therefore, plant design philosophy is observed characteristically in selection of them.   This paper describes the evaluation and analysis of the essential concepts of the HTGR-GT power conversion system through the investigations based on our experiences and engineering knowledge as a fabricator. As a result, the following concepts were evaluated that have advantages against other competitive one, such as the horizontal turbo machine rotor, the turbo machine in an individual vessel, the turbo machine with single shaft, the generator inside the power conversion vessel, and the power conversion system cycle with an intercooler. The results of the study can contribute as reference data when the concepts will be selected.   Furthermore, we addressed reasonableness about the concept selection of the Gas Turbine High Temperature Reactor GTHTR300 power conversion system, which has been promoted by JAEA. As a conclusion, we recognized the GTHTR300 would be one of the most promising concepts for commercialization in near future.

著者

山田 進 町田 昌彦 有川 太郎

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.22, no.2, pp.73-86, 2023 (Released:2023-04-27)

参考文献数

24

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A siltfence is installed to prevent the spread of suspended sediments generated by engineering construction works in rivers and on the coast. Thus, the siltfence is regarded to be a tool to prevent radioactive materials adsorbed on suspended sediments from diffusing into the sea in ports of nuclear power plants during nuclear accidents. However, the prevention effects of the siltfence as sediment control structures have not yet been fully evaluated. Therefore, in this paper, we simulate the behaviors of suspended sediment particles using a coupled simulation scheme composed of water flow and deformation of the siltfence in a rectangular open channel under uniform steady flow, and evaluate the promotive effects of the installed siltfence on suspended sediment deposition. The results demonstrate that the installation of the siltfence significantly promotes deposition, especially of particles with low settling velocities. However, it should be noted that the opposite case is also possible, i.e., the siltfence promotes the diffusion of suspended sediments under particular conditions. These results suggest that a careful installation strategy is necessary. The present simulation scheme is useful in assessing the prevention effects of siltfences prior to their installation.

著者

眞田 幸尚 操上 広志 舟木 泰智 吉村 和也 阿部 智久 石田 睦司 谷森 奏一郎 佐藤 里奈

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.20, no.2, pp.62-73, 2021 (Released:2021-06-01)

参考文献数

29

被引用文献数

1 4

---

The Japanese government is beginning to consider radiation protection in the “specific reconstruction reproduction base area” of the Fukushima nuclear power plant, the evacuation order of which will be lifted by 2023. It is essential to grasp the present situation of radiation contamination and evaluate exposure dose in the area to realize the lifting of this evacuation order zone. Many surveys on the evaluation of the distributions of air dose rate have been carried out, and exposure dose has been estimated using the results since the Fukushima Daiichi Nuclear Power Plant accident. Nevertheless, more detailed information on exposure is needed for the area because the radiation level is relatively high. This will also be helpful in preparing a prudent evaluation plan. This study is aimed at evaluating the detailed contamination situation in the area and estimating exposure dose with consideration of areal circumstances. Work was carried out for (1) an airborne survey of the air dose rate using an unmanned helicopter and ground-based measurement (walk-survey), (2) the evaluation of airborne radiocesium and (3) the estimation of external/internal effective doses for the typical life patterns assumed. Our study resulted in a detailed map of the air dose rate and clarified the distribution pattern in the area. Moreover, the exposure dose of residents was evaluated by considering some life patterns based on this map.

著者

角田 淳弥 植田 祥平 國富 一彦 吉牟田 秀治 沢 和弘

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.2, no.4, pp.546-554, 2003-12-25 (Released:2010-03-08)

参考文献数

29

被引用文献数

2 2

---

A High Temperature Gas-Cooled Reactor (HTGR) is particularly attractive due to capability of producing high temperature helium gas and its inherent safety characteristic. Research and development of high temperature gas turbine plant and high temperature heat utilizing technology are now undergoing. The High Temperature Engineering Test Reactor (HTTR) is a research facility constructed by the Japan Atomic Energy Research Institute (JAERI). All rise-topower tests have been successfully carried out and the performance of the HTTR has been evaluated. Now, preparation for the operation with outlet coolant temperature of 950°C and safety demonstration tests are undergoing.This paper describes reprocessing technology of HTGR fuels. Coated fuel particles, consisted of a microsphere of low enriched UO2 with TRISO particles, are used as the HTGR fuels. In order to reprocess HTGR fuels, a head-end process is needed and JAERI had confirmed jet-grind method as basic technologies of the head-end process. Since Purex method can be used after the head-end process, a reprocessing system for the HTGR fuels could be established. Also the preliminary study on the methodology for disposing graphite blocks in a HTGR was carried out, and its evaluation results were briefly presented.

著者

深谷 裕司 大橋 弘史 佐藤 博之 後藤 実 國富 一彦

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

pp.J21.005, (Released:2022-03-30)

参考文献数

33

被引用文献数

1

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An improvement of the electricity generation cost evaluation method for High Temperature Gas-cooled Reactors (HTGRs) has been performed. Japan Atomic Energy Agency (JAEA) had completed the commercial HTGR concept named Gas Turbine High Temperature Reactor (GTHTR300) and the electricity generation cost evaluation method approximately a decade ago. The cost evaluation was developed on the basis of the method of Federation of Electric Power Companies (FEPC). The FEPC method was markedly revised after the Fukushima Daiichi nuclear disaster. Moreover, the escalation of material and labor costs for the decade should be considered to evaluate the latest cost. Therefore, we revised the cost evaluation method for GTHTR300 and the determined cost was compared with that of the Light Water Reactor (LWR). As a result, it was found that the electricity generation cost of HTGR of 7.9 yen/kWh is cheaper than that of LWR of 11.7 yen/kWh by approximately 30% at the capacity factor of 70%.

著者

山本 晃弘 関村 直人

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.16, no.3, pp.119-138, 2017 (Released:2017-08-15)

参考文献数

59

被引用文献数

2 1

---

The enhancement of safety culture is an issue for both plant operators and regulators working in fields related to the safety management of nuclear power plants. Plant operators have been collecting safety culture data through a broad range of tools and methods such as observations, interviews and other surveys. However, many issues remain regarding the effectiveness of safety culture activity. A new regulatory authority was established in 2012 after the Fukushima Dai-ichi accident to enforce nuclear safety regulations but its activity is still weak in terms of monitoring the performance of plant operators’ safety culture. In order to promote and strengthen safety culture, plant operators need to collect detailed event information, even when events do not directly affect plant safety, and accumulate information related to human, organizational and technical factors through dialogue among the parties responsible for coping with events. Both operators and regulators should all be working in the same direction to assess information that will help their periodic reviews, and the involvement of local government is a key to enhancing their safety culture.

著者

山崎 正俊 宇根崎 博信

出版者

Atomic Energy Society of Japan

雑誌

日本原子力学会和文論文誌 (ISSN:13472879)

巻号頁・発行日

vol.9, no.3, pp.243-251, 2010 (Released:2012-02-08)

参考文献数

8

被引用文献数

1 1

---

For the sake of more efficient operation of nuclear power plants and to reduce the number of spent nuclear fuel assemblies, increasing uranium enrichment is one of the rational options. However, current uranium enrichment for the whole fuel cycle infrastructure is limited to no greater than 5 wt% from the view point of criticality safety. In this review, three main topics are discussed: 1) the necessity of increasing the uranium enrichment above 5 wt%; 2) current status and challenges to go over 5 wt% enrichment; and 3) proposal of the “Erbia Credit Super High Burnup Fuel” as a measure to break the “5 wt% enrichment barrier.” The third topic is further elaborated on by discussing the introduction scenarios before concluding with a mention of the necessity of a best-mix analysis for this concept in the fuel cycle supply chain.

著者

福島 公親 飯田 式彦

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.1, no.2, pp.144-152, 2002-06-25 (Released:2009-03-16)

参考文献数

13

---

Conventional nuclear reactors converge energy produced by fission to thermal energy of point nuclei, and subsequently to electric power by means of turbines. The conversion efficiency of fission energy to electric power in these systems has not yet gone beyond thirty-odd percent, and almost all applications are restricted to power generation. On the other hand, the collision theory since Rutherford's study indicates that the energy of a charged particle is transferred preferably to an electron with light mass by collision, except for the case of a low velocity charged particle where energy is transferred to a point nucleus with heavy mass. By using electrodynamics this paper shows the possibility that energy of a fission fragment can be transferred preferably to an electron in an atom such as rare gas by collision, and that the emitted energy of a secondary electron is transferred preferably to an electron in a rare gas atom by excitation caused by the collision. Thus, as a result of the photon emission from excited electrons in the rare gas, nuclear energy can be converted to photon energy. The photon energy emitted and the transition probability are derived by the first-principle electronic state analysis. Applications of this technology may possibly lead to the construction of new and various photoindustries.