IISSSSNN アトックス技報 ATOX TECHNICAL REPORT No

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1 IISSSSNN アトックス技報 ATOX TECHNICAL REPORT No

2 アトックス技報 No Measurement

巻頭言 Preface 東日本大震災からの復旧復興に向けてアトックス一丸となって取り組みます取締役社長矢口敏和アトックス技報第 3 号の刊行にあたりご挨拶申し上げますアトックスはビルメンテナンスを手がけるビル代行より 1980 年に分離独立して原子力代行として発足 1993 年に商号変更し昨年 2010 年に設立 30 周年を迎えました現在では国内すべての原子力発電所

震災直後こそ当社社員自身が被災したこともあり一時混乱した時期もありましたが他事業所の社員や協力会社の支援も得て早い段階から会社を挙げて各被災発電所等の復旧作業に取り組む体制を整えることができました取り分け福島地区では 4 月に福島復興本部を立ち上げ福島第一原子力発電所を中心に相次ぐ復旧作業の支援要請に積極的に応えてきました

3 巻頭言 Preface 東日本大震災からの復旧復興に向けてアトックス一丸となって取り組みます取締役社長矢口敏和アトックス技報第 3 号の刊行にあたりご挨拶申し上げますアトックスはビルメンテナンスを手がけるビル代行より 1980 年に分離独立して原子力代行として発足 1993 年に商号変更し昨年 2010 年に設立 30 周年を迎えました現在では国内すべての原子力発電所原子燃料サイクル施設に事業所を設置し種々のサービスを提供するとともに原子力研究機関大学等の放射性物質を扱う施設においても運転保守等を支援し原子力施設のトータルメンテナンス会社として事業を展開しております今般の東日本大震災では地震当日数多くの当社社員及び協力会社社員が被害を受けた福島第一第二原子力発電所や女川東海原子力発電所等で働いていました震災直後こそ当社社員自身が被災したこともあり一時混乱した時期もありましたが他事業所の社員や協力会社の支援も得て早い段階から会社を挙げて各被災発電所等の復旧作業に取り組む体制を整えることができました取り分け福島地区では 4 月に福島復興本部を立ち上げ福島第一原子力発電所を中心に相次ぐ復旧作業の支援要請に積極的に応えてきましたそのなかには冷温停止の鍵を握る汚染水の浄化システムの運転管理業務も含まれます現在では福島在住の社員を中心に 800 人を超える人員が福島地区で復旧作業に従事しています当社が現在あるのは言うまでもなくわが国原子力産業の成長と発展のおかげですこれまでの恩に報いるためにも今こそ当社はこれまで培ってきた現場力技術力そして地域密着力を最大限活かし率先してその復旧復興に貢献しなければならないと考えています同時にそのことが当社の将来を開く唯一の道だという思いを社員全員で共有し全社一丸となって取り組み延いては原子力産業に対する信頼回復の一旦を担っていきたいと強く願っています当社の技術開発センターは 1988 年の開所以来電力会社等との共同研究も含め常に現場に密着し現場で必要とされる技術や工法の開発に力を注いできました今後はこれまでの成果やノウハウを活かし福島第一原子力発電所の収束作業や周辺地域の環境修復作業などでこれから必要とされる技術なかでも除染やロボットを含むリモートコントロール技術廃炉関連技術等現場の課題解決に繋がる技術の開発を最優先テーマとして取り組んでいく所存ですアトックス技報は当社の技術開発の成果や活動を電力研究機関等をはじめとするお客様にご紹介するために関係者の皆様のご理解とご協力を頂いて 2010 年 1 月に第 1 号を発刊以来今回で 3 号目となります本技報を多くの方々にご覧いただきご意見ご批評を賜れば幸いに存じます今後とも皆様のご指導とご鞭撻を賜りますようよろしくお願い申し上げます平成 23 年 12 月吉日 ATOX TECHNICAL REPORT No

4 R&D Activities Cesium Adsorption Characteristics of Selected Natural Zeolite Zeolite is effective in decontamination of radioactive liquid containing cesium. To contribute to the environmental remediation after the NPP severe accident, adsorption tests of cesium from sea water were conducted on selected natural zeolite, mordenite and chlinoptilolite, with different particle sizes, produced in Japan. The observed distribution coefficients of the zeolite in the cesium adsorption have shown large particle-size dependence. It was confirmed that a column packed with small size zeolite can effectively decontaminate environmental water slightly contaminated with radioactive cesium. Key WordsNatural Zeolite, Mordenite, Clinoptilolite, Cesium, Adsorption TMI-2 1) 2) 3) 3 0.5mm, 13mm, 35mm 3 5m, 250 m, 0.51mm, mm, 35mm, 79 mm 1g 99ml 1ml 10ppm 70 /min ml ICP-MS Cs Kd ml/g 1g 1m Kd(t) Co t Ct V(ml) m (g) Kd(t) = (Co CtV / Ct m (23) Cs Kd 0.5mm が速いことが分かる Kd mm 13 mm 35 mm アトックス技報 No

R&D Activities 3mm Kd Cs Kd 5250m 80 400 5µm 250µm 300 0.51mm Kd 150 100 50 0 500 200 100 0.51mm 35 mm 79 mm 1 3 24 48 0 1 3 24 48 5.5 cm 50 cm 0.51mm 134 Cs, 137 Cs 10 /hr 4 0.

5 R&D Activities 3mm Kd Cs Kd 5250m µm 250µm mm Kd mm 35 mm 79 mm cm 50 cm 0.51mm 134 Cs, 137 Cs 10 /hr 4 0.2m 134 Cs, 137 Cs Cs 130ppb 97/hr 88 Kd Kd 450 Kd 250m 1m 3 /hr 1mm 2011 ) 1) The Three Mile Island Accident, Ed by L. M. Toth, A. P. Malinauskas, G. R. Eidam, H. M. Burton, Am. Chem. Soc. (1986). 2),,,,,, 35 (1), (1979). 3), 4),,,,,,,, D13 (2011). Gr. Gr. Gr ATOX TECHNICAL REPORT No

R&D Activities Decontamination Examination for the Environmental Remediation Private houses, public

were contaminated with radioactive fallout from the Fukushima Daiichi Nuclear Power Plants accident

For inhabitants, the environmental remediation with decontamination is the most important and urgent

Decontamination tests were carried out for houses in the planned evacuation area, schools and kindergarten

6 R&D Activities Decontamination Examination for the Environmental Remediation Private houses, public buildings (school, park etc.), farmland, forests etc. were contaminated with radioactive fallout from the Fukushima Daiichi Nuclear Power Plants accident following the earthquake. For inhabitants, the environmental remediation with decontamination is the most important and urgent action. Decontamination tests were carried out for houses in the planned evacuation area, schools and kindergarten in the non-restricted area in Date-city, and houses and orchards in the specific evacuation area. Effective decontamination methods were verified and some issues were identified. Key WordsReactor Accident, Radioactive Contamination, Decontamination, Environmental Remediation NPO 1) JPDR 2) mm 1520Sv/h 50Sv/h 1050% 7.5 m/min 90% アトックス技報 No

7 R&D Activities 1mSv0.10.2Sv/h 3) 1mSv % mSv 5mSv11.5Sv/h 3070% 50% 20m18m 2.0Sv/h 0.6Sv/h Sv/h 50 5cm 1mSv Sv/h 1), NPO, ) JPDR 38(7) p.564(1996) 3) ATOX TECHNICAL REPORT No

8 RR&D D Activities Activities Development ofof the Non-Releasing Liquid-Waste Electrolytic Decontamination Device Development Non-Releasing Liquid-Waste Electrolytic Decontamination Device The electrolytic decontamination enables us to decontaminate a variety of metal-wastes contaminated with radioactive substance, and also to do remote decontamination. Therefore, this method is suited to the work under a radioactive environment. The problem on this technology is the generation of the large amount of electrolytic liquid-waste. We made a study of a new electrolytic solution to solve the problem. As the result, we have almost developed the type of non-releasing liquid-waste electrolytic decontamination device, which enables us to work without changing the deterioration of electrolytic solution. Key WordsDecontamination, Electrolytic Decontamination, Electrolytic Solution, Liquid-Waste Treatment 1) アトックス技報 No No Na + OH + + (OH) OH + e OH 6

9 D Activities RR&D g 2 1m L 5 % 40A 2 0.1A/cm h g ) 9 22 pp Gr. Gr. ATOX TECHNICAL REPORT No ATOX TECHNICAL REPORT No

10 R&D Activities Development of Ultrasonic Thickness Measurement Robot for Penstock The ultrasonic thickness measurement of Penstock in the hydraulic power plant is carried out on the scaffold placed around it. Therefore, the high cost for work and the safety measures become a problem. In order to solve these issues, a prototype machine which has a ultrasonic thickness measurement instrument and a function of driving outer side of Penstock was developed. Key WordsPenstock, Nondestructive Testing, Ultrasonic Thickness Determination, Inspection Robot 360 W 370L 540H 180mm 20kg 130mm/sec 1,200mm アトックス技報 No

R&D Activities 100mm DC 110 11mm 5 30mm 100 9 25 4 100mm 360 2 mm A B C 9.52 9.52 9.52 9.51 9.

11 R&D Activities 100mm DC mm 5 30mm mm mm A B C mm 100 Gr ATOX TECHNICAL REPORT No

12 R&D Activities Development of Remote-Controlled Self-Propelled Plasma Cutting Machine At the working area of demolition of a heat exchanger and the waste treatment at a nuclear power plant, radiation level of the area is very high due to radiation from the heat exchanger. Therefore, a remote controlled self propelled plasma cutting machine was developed to reduce radiation exposure to the workers. Key WordsCuttingRemote-ControlledSelf-PropelledPlasmaHeat Exchanger SUS316 6,383mm 880mm 44mm SB410 6,195mm 720mm 12mm アトックス技報 No

13 R&D Activities SUS304 SS400 10,20,30,40,50mm mm/min SS400 6mm 2 765mm/min Gr. Gr ATOX TECHNICAL REPORT No

14 R&D Activities Development of Blower Blast Decontamination Method Large amount of radioactive metallic waste is generated by decommissioning of nuclear power plants and nuclear facilities. A dry blast decontamination method is effective for metallic waste, because it doesn t need liquid waste treatment. In this development, the applicability of the blower blast to decontaminate was confirmed. Key WordsDecommissioning, Blast Decontamination, Blower Blast 1/3 0.45MPa 0.08MPa アトックス技報 No

R&D Activities 0.5mm SS400 W1,250 D1,250 H2,600 3.7kW 0.08MPa 0.9m³/min 8 W1,030 D1,050 H2,630 W2,180 D 900 H1,510 15kW 0.

15 R&D Activities 0.5mm SS400 W1,250 D1,250 H2, kW 0.08MPa 0.9m³/min 8 W1,030 D1,050 H2,630 W2,180 D 900 H1,510 15kW 0.5MPa 1.9m³/min 6mm SS g/min 0.40g/min 15kW 3.7kW kw 0.083g/min 0.108g/min Gr. Gr. Gr ATOX TECHNICAL REPORT No

16 R&D Activities Development of Stable Processing Unit for BF 3 Gas Enclosed in NIS Detector NIS BF 3 BF 3 NIS NIS BF 3 BF 3 gas enclosed in the neutron detector (Neutron Instrument System detector) for nuclear power plant is poisonous gas which generates corrosive acid mist in the air. A stable processing unit for BF 3 in NIS detector was developed. Using the processing unit, BF 3 gas was extracted safely, and stabilizing treatment was carried out with not alkaline water, but water with lower salt concentration. The safety and the capacity reduction efficiency were demonstrated. Key WordsNIS DetectorBF 3 GasGas ProcessingStabilization NIS NIS NIS BF 3 NIS BF 3 NIS BF 3 NIS MSDSBF 3 BF 3 BF 3 HF BF 3 B HF BF 3 BF 3 BF 3 HF HF 3ppm 1/10 0.3ppm BF 3 ph= ph= mm 25 HF 0.25ppm 0.1ppm BF 3 ph NaFH 3 BO 3 HF アトックス技報 No

17 R&D Activities BF 3 H1,100D600W1,050mm 120kg 10L2 BF 3 100% %BF 3 10mm 1mol/L 100ppm 99.97% BF 3 HF BF 3 1mol HF3mol HF HF BF 3 HF MSDS HFHF HF BF 3 BF 3 2 BF 3 BF 3 BF 3 BF 3 NIS Gr ATOX TECHNICAL REPORT No

18 R&D Activities Analysis of F - in Zinc Acetate DZA F - IC DZA Zn F - F - Depleted Zinc Acetate (DZA) is used in nuclear power plant. In order to determine the level of impurities in DZA, it is necessary to analyze very small amounts of many elements. Fluoride ion (F - ) is one of the impurity elements, and in general, ion chromatography determination (IC) is often used for trace analysis of F -. But acetate and zinc ions hinder this analysis by IC. Therefore, the F - analysis method was examined and improved based on the official method (JIS). As a result, trace amounts of F - in DZA was able to be analyzed by changing the conditions of the steam distillation method and spectrophotometric determination using alfusone. Key WordsFluoride IonSteam DistillationSpectrophotometric Determination with Alfusone DZA DZA 1) F - IC ZA F - ZA IC F - F - Zn 2+ ZA F - ZADZA F - 2) F - F - No.1F - F - 72% No.1 SiO 2 F - SiO 2 No.2,3 SiO 2 F - 100% No.1 No.2 No.3 JIS SiO 2 0.1g SiO 2 SiO 2 g ml F[g] [min] No.1 No.2 No.3 No.1() No.2() No.3() F : 100g 10 : 5060ml SiO 2 F - JIS F[%] アトックス技報 No

19 R&D Activities 30 F - F - 100% ml 200ml 10F[g] ±5 135±5 145±5 125±5 () 135±5 () 145±5 () [min] F[g] : No.1 = 100 No.2, 3 = 50 10[ml] : 5060 SiO2 : F F[%] 1/10 50mm F - F - ph 4) a F - ph a (F 5µg) b (F ) IC F - SO 4 2- HPO 4 3- F [ml] S [] F - IC Na + IC IC F - 620nm10mm 1g /g 10mm 50mm 5 50mm F - 3) F - S [] F - F - F - SiO /10 ph 1),, 2009, pp.21-22, )JIS K 0102pp ) 2pp ) R. Greenhalgh. And J. P. Reley, Anal. Chim. Acta., , Gr ATOX TECHNICAL REPORT No

20 トピックス Topics アトックス技報 No

21 トピックス Topics m5m 8m ATOX TECHNICAL REPORT No

22 アトックス情報 ATOX Information 60 Co 1.137PBq 60 Co 0.7PBq ) Gy/h 6m 8m 5m Co 100/200V ,000 アトックス技報 No

23 アトックス情報 ATOX Information BeUSEM XPS XAFS ICP ICP-MS ICP-MS SEM XPS X XAFS Ge % ATOX TECHNICAL REPORT No

24 アトックス情報 ATOX Information H H H H H H H H H H H H H H H H BF 3 BF H H H H H H H H H H H H H H H H H H アトックス技報 No

アトックス情報 ATOX Information 3410mm 2 2 1 2 3 454 11 22

25 アトックス情報 ATOX Information 3410mm ATOX TECHNICAL REPORT No

26 アトックス情報 ATOX Information , アトックス技報 No

27 F FAX NDL-OPAC NDL-OPAC No ATOX TECHNICAL REPORT No.3 December 2011 Published and Edited by Engineering Research & Development Center ATOX CO.,LTD , Takata, Kashiwa-shi, Chiba TEL TEL FAX FAX URL

1 2 *1 JIS A X TEM 950 TEM JIS Development and Research of the Equipment for Conversion to Harmless Substances and Recycle of Asbe

*1 *2 *1 JIS A X TEM 950 TEM JIS Development and Research of the Equipment for Conversion to Harmless Substances and Recycle of Asbe *1 *2 *1 JIS A 14812008X TEM 950 TEM 1 2 3 4 JIS Development and Research of the Equipment for Conversion to Harmless Substances and Recycle of Asbestos with Superheated Steam Part 3 An evaluation with