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玫汲
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1 類路理力梁 94 年年年 12 22

2 行路理數 27 / 聯 / 力 / / / / 梁 / 力 / / 類 /11/27-94/12/03 94/12/16 類 / 路 - Kashiwazaki-Kariwa NPS K6/K7 Hamaoka NPS H-5 Seika NPS S-2 Startup Test 路理降路輻率輻度輻領 Hitachi Toshiba 論輻量降 RWCU 量率 50% 路 20% 不路行流 Reactor Vessel Flow Induced Vibration Test, FIV 不來行 http //report.gsn.gov.tw 1, 27

3 行輻量來輻量來 Co Co-60 料 Co 路 Simple is Beauty 理理理念 - 降度降度 - 路路理 Hitachi 路 Nuclear Heatup 理 FIV test 理 Hitachi 路路理輻量 Toshiba 路 Toshiba , 27

4 3.1 爐略 Co 料不 CoO 度 CoFe 2 O Co NWC 不 Ni 度 Co NWC Fe 度 Co HWC 不 Cr 度不略度 Co 不路理不 Co 不 Co Nuclear Heatup 理流 Nuclear Heatup FIV test 理流 FIV test 理流 Na- NH + 4 SO 2-4 離理粒更更理降率理降 RWCU 輻量率 , 27

5 3.1 爐度例 BWR ABWR 量 25 4, 27

6 - Kashiwazaki-Kariwa NPS K6/K7 Hamaoka NPS H-5 Seika NPS S-2 Startup Test 路理降路輻率輻度輻輻度輻量率降輻度量率力爐 Reactor Water Cleanup System, RWCU 爐烈 active corrosion product 易路輻來 RWCU 12.5 % 量量來 1 RWCU 路量降量 ALARA 若良輻量輻念量 Dose constraint Source constraint 流 2 RWCU 路 Hitachi Toshiba 論路行 1 年量 RWCU 量量 12.5% 2 ICRP-60 輻量 Dose Constraint Source Constraint 5, 27

7 參行 94 年六 7 參 Hitachi Toshiba Toshiba 不 Hitachi Dr. Motomasa Dr. Kanai 行 1. 11/ /28-11/29 Hitachi 3. 11/30 Dr. Kanai Toshiba 路 4. 12/01 Hitachi 立 Kaigan Factory 力 Power & Industrial System R&D Lab /02 參 Hitachi 行 Dr. Motomasa Chief Engineer, Nuclear Plant Service Engineering Department Dr. Motohiro Senior Engineer, Water Chemistry Preventive Maintenance Engineering Section Dr. Makoto Senior Researcher, Nuclear Chemical Project Dr. Hiroo Senior Engineer, International Project Management Department Dr. Kazuhiro Senior Engineer, Procurement Control and Promotion Group 論路 6, 27

8 路行參路不降度 activated corrosion product, ACP 量 Startup Nuclear Heating Test FIV Test 不更路 Hitachi Toshiba 路歷路量路 3.1. 輻量輻量來輻量來路料流爐 ACP 路來路料不 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Cu-64 Zn-65 PSAR 量 Cr-51 量率 Co-58 Co-60 Cr 爐輻例 E r (MeV) I r (%) 度例輻例 (%) Na h Cr d Mn d Mn h Co d Co a Fe d Cu h Zn d % 輻量來 Co-60 Co-60 7, 27

9 路輻量 Co-60 路量 3.1 dγ dt = δc λγ (3.1) Γ Co-60 路量 δ Co-60 率數 deposition rate coefficient C 流 Co-60 度 Co-60 數 3.1 不爐 Co-60 略 chemical decontamination 量 2. Zn injection 爐 Low Fe/High Ni Control 理 electrical mechanical polishing air oxidation treatment 降率 3. 料 low cobalt material 爐 Low Fe/High Ni Control RWCU 量 Co-60 度 3.1 爐略 8, 27

10 不不例 70 年不爐 CRUD 3 量輻量不 80 年料冷濾 Prefilter RWCU 量 1% 2% 5% 爐爐力 Fe 度 ppb 輻量年輻量 Co-60 Fe Co Ni 路料不量 Co Ni 流路量 Co Ni 量 Co-60 Co-58 Co-60 路輻輻量了行略 Co-60 料 3.2 Co-60 料度 Co BWR 料 CoFe 2 O 4 spinel 易 CoO 兩不 Fe 2 O CoFe 2 O 4 CoO 不 ph 度 BWR CoO 度 CoFe 2 O 4 10 Co / BWR Co / 兩 1. 量 / High Fe / Low Ni Control [Fe/Ni] > 2 CoO 料年行理論 CoO 料 Co-60 3 CRUD Chalk River Unidentified Deposition 4 Toshiba Co. (2005), Experiences with Water Chemistry of Toshiba s ABWR, presentation documents. 9, 27

11 兩 CoO 路 Co 3.2 Co 料 3.3 不 CoO 度 CoFe 2 O , 27

12 2. 量度 Low Fe Control [Fe/Ni] < 2 來 CoO 料爐 Co-60 度 CoO 易 RWCU RWCU 濾來 CoFe 2 O 4 RWCU Co-60 例行輻量率量利離來 BWR 略 Fe 度 Ultra Low Fe Control Co 路 Co-60 路異不量 Cr Ni α-fe 2 O 3 Ni x Fe 3-x O 4 Cr x Fe 3-x O 4 Fe Co Ni Cr 離 Co 行 3.4 Co NWC 不 Ni 度例 Normal water Chemistry, NWC Co 不 Ni Fe NiCo x Fe 3-x O 4 Cr Fe x Cr 3-x O 4 Ni/Co Fe M x Fe 3-x O 4 [Ni 2+ ] 度離 CoFe 2 O 4 Co-60 路 11, 27

13 3.5 Co NWC Fe 度 Co Ni Cr 量不 [Fe 2+ ] 離 / 不行料 Fe 2 O 3 [Fe 2+ ] [Co 2+ ] 離離 Co Co HWC 不 Cr 度 12, 27

14 HWC Co 不 CoFe 2 O 4 CoCr 2 O 4 率 HWC 輻量 NWC 3.2. Simple is Beauty 理料路力裂 Intergranular stress corrosion cracking, IGSCC 路爐裡離 Hydrogen chemistry Zinc injection 金 Noble metal chemistry 爐 Low Fe/High Ni Control 不理例 SCC 不輻量金輻 SCC 不 3.7 不略 13, 27

15 90 年 ABWR 理理念力裂料理 3.7 行輻量 ABWR 爐不金 Simple is Beauty ABWR 良降 Fe 度路輻理理念 - 降度 3.8 不 [Fe] 度 Co 3.1 Co-60 率數 deposition rate coefficient = k / t 度 Low Fe Control Co-60 不 / Low Fe/High Ni Control 率 2-4 Co 不率數 SCC 例不料 3.8 度 Co 不降度 - 路 ABWR [Fe] 度降 0.1 ppb 度 Fe 度降 CoFe 2 O 4 CoO 冷 Condensate polishing system RWCU 量 14, 27

16 3.7 輻料 RWCU 量冷 Prefilter Fe 度 0.25 ppb ppb 列 Fe 度 0.1 ppb RWCU 路 piping passivation 降 Fe 度行路理路率 / 料度度 BWR 理降度度數年量 Co-60 輻量不路理力路 5 GE Company (1997), Plant Working Fluids Requirements, A EOC 料數 ppb 1.60 ppb ppb 1.35 ppb 15, 27

17 3.2 RW < 200 o F Operating Target Design Limit Fuel Warranty EPRI 2000 Action Level I EPRI 1986 Action Level I Total Fe < Total Cu < All Other Metal < RW 200 F Total Fe < Total Cu < All Other Metal < Power Operation Total Fe < Total Cu < Total Zn All Other Metal < EPRI-2000 [Fe] Action Level I 5.0 ppb ppb 不狀 0.1 ppb 度

18 路降度理念 1986 年 EPRI BWR 理 304 不 NWC 狀 Co-60 率理 1/ 屢屢 IGSCC 304 不 Hitachi Toshiba 理念不路參 3.10 理不 Co Electric Power Research Institute (1986), BWR Normal Water Chemistry Guidelines: 1986 Revision, EPRI NP-4946-SR. C. C. Lin (1986), BWR Cobalt Deposition Studies, EPRI NP , 27

19 3.3. Hitachi 路 Hitachi 路良度量金離 Co 不 Co-60 理不 Co-60 降理 1/4 不 Hitachi 降 1/3 輻量 3.11 不 Co-60 Hitachi 路良 BWR 不路 Hitachi Nuclear heatup FIV test RIP 度 RWCU H-form Na-form 爐 18, 27

20 ph 度 100 ppb Heatup ppb FIV test Nuclear Heatup 理 3.12 Nuclear Heatup RWCU 理路流 RWCU Filter Demineralizer A 串 Na-form B 串 H-form 爐 ph 3.12 Nuclear Heatup 理流 280 o C 100 ppb ph Heatup 19, 27

21 19 不 3.13 Nuclear Heatup FIV test 理理理行 FIV test RIP GE 9 FIVtest 度 160 o C 理度 o C 度 FIV test 理流 FIV test 度 o C 500 ppb ph FIV test Pre-OP test 9 GE Company (2002), Nuclear Islands System Preoperational Test Specification, A , 27

22 3.14 FIV test 理流 3.15 FIV test 理流 21, 27

23 Nuclear heatup 流度 Na- H- CST 爐理 dump 料 Hitachi 路兩 FIV test 80 更料不不利 Na- NH + 4 SO 2-4 離 3.16 爐 Inconel 金狀料不 Nuclear Heatup Nuclear Heatup FIV test 量 FIV 3.16 Na- NH 4 + SO 4 2- 離路 22, 27

24 金離離 10, SEM 12 理理粒度路路 3.17 理粒更更 3.18 說不路路理路 50% 10-30% 不路 13 RWCU 路 14 力 3.18 路 10 年歷 3.19 路理狀 F K-5 BWR-5 G K-6 Toshiba ABWR H K-7 Hitachi ABWR Toshiba K-6 / Toshiba 數理降 2-4 輻量 10 Takashi Honda et al. (1987), Deposition of radioactive ions on boiling water reactor component materials, Corrosion, 43, G. Romeo (1983), Oxidation and radiation buildup on stainless steel components of boiling water reactors, Nuclear Technology, 63, Takashi Honda et al. (1990), An alkaline prefilming process for the primary piping in a new Japanese boiling water reactor, Nuclear Technology, 89, Takashi Honda et al. (1987), Suppression of radiation buildup on stainless in a boiling water reactor, Corrosion, 43, Under vessel 65 mm 路 TP316L 路 A333 GR6 路 A106 GRB 兩 23, 27

25 3.18 理降率不,, 率 3.19 理降 RWCU 輻量率 2-4 F K-5 (BWR-5) G H K-6 K-7 (ABWR) 24, 27

26 理輻量 3.3 BWR-5(K-5 ) 15 ABWR(K-7 ) 量 16,17,18 路 RWCU 量 40-50% 3 年 RWCU 量 man-msv 路 70 man-msv 量 3.3 BWR ABWR 量 - BWR-5 ABWR EOC #1 EOC #1 EOC #13-15 Drywell Drywell ISI Valve Inspection Recirc. Pump Related Sump Related CRD Related RIP Inspection Others Reactor Building RWCU Related Well Decon RHR Related Others Turbine Building Misc. Inspection Others TOTAL K-5 路理降輻量 16 N. Suzuki et al. (1999), An ABWR water chemistry control design concept for low radiation exposure and the operating experience at the first ABWR, Hitachi internal document. 17 H. Masui (1998), ALARL program in the new generation of advanced BWRs, TEPO internal document. 18 K. Ohsumi et al. (1989), Improved water chemistry control of radiation reduction for the latest BWR and proceeding BWR, in: Proc. International Workshop on New Developments in Occupational Dose Control and ALARA Implementation at Nuclear Power Plants and Similar Facilities, Brookhaven National Lab., New York. 25, 27

27 40 年 18 料 3,800 man-msv 量 man-rem 量 10,000 金路省 380 金 12,500 輻更 3.4. Toshiba 路 Toshiba Toshiba 路 Startup Ni Zn Fe Cr Mn Cu Pd Pt Al Mo V W 金 Co 離 19 Toshiba 爐 [Ni] 5 ppb 數數不 K-6 理輻度不 Toshiba 5 H-5 路 K-6 Toshiba H-5 理 Post welding Heat Treatment, PHT 路 ASME 30 cm 425 o C PHT Toshiba Oven RWCU 度 2 PHT 理路理 Oven 不 RWCU 不 PHT 復理論更理度度粒易降 Toshiba 理 2 度路行參 19 (1996), 力 Toshiba Co. (2005), Experiences with water chemistry of Toshiba s ABWR, Toshiba internal document. 26, 27

28 參見路良度不不更不來量輻量力 ALARA 輻 1 行落 95 年行行路 2 料參 Hitachi Toshiba 年領 Hitachi 例 90 年領 300 略略力年兩不 Simple is Beauty 理理略 EPRI 理念不更 27, 27

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