KAERI/CR-111/2001
RN113
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Study on the Evaluation of Decontamination & Decommissioning Technologies and Their Demands in Korea
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Portions of this document may be illegible in electronic image products. Images are produced from the best available original document. KAERI/CR-111/2001
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Study on the Evaluation of Decontamination & Decommissioning Technologies and Their Demands in Korea
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SUMMARY
1. Project Title Study on the Evaluation of Decontamination & Decommissioning Technologies and Their Demands in Korea
2. Objectives of the Project Most of the developed countries including USA, UK and France are expected to stop construction of new nuclear power plants for the time being and to extend the existing NPP and also to decommission the nuclear facilities mainly related to the back end nuclear fuel cycle development activities. Decontamination and decommissioning (D&D) in these countries becomes one of the most important nuclear industry. D&D of the TRIGA MARK II and III, the first nuclear reactor in Korea has been already started. Considering the importance of the decontamination and decommissioning, it is time to launch the national D&D technology development program. The purpose of the study is to evaluate the D&D technology demand and its current status to screen the necessary technologies for the national R&D program and then is to identify the development circumstance and future prospects of the selected technologies necessary to the R&D planning.
3. Contents and Scope of the Study D&D market in Korea as well as abroad was classified into three fields such as a research reactor, a commercial nuclear power plant and a nuclear fuel cycle and then forecasted by 2010 as a short term demand and also by 2030 as a long term demand. A technology tree diagram was developed by classifying into the lower level of the technologies up to 3 or 4 level and then the current status of the final technology items were evaluated by using the evaluation criteria. KOPEC select the technologies subject to development in the short term and also in the long term. The short term('01-06) development
v technologies were further analyzed into its technology tree and then evaluated their future prospects.
IV. Results The domestic D&D market ie expected to increase gradually in the future and the large D&D market has been already formulated abroad, especially in the U. S. A. mainly for the nuclear fuel cycle facilities. The short term D&D needs in the country will be the decommissioning for the TRIG A research reactors and the uranium conversion facility we are facing, the back end nuclear fuel cycle development facilities for maintenance and refurbishment, and the nuclear power plants for operation and maintenance including the plant life time extension. The demand of the nuclear fuel cycle R&D facilities in North Korea also will be gradually increased depending on the reunification of the Korean peninsular. The short term R&D items were selected using the above results by KOPEC. The technology tree was analyzed in the study as follows: Level 0 Level 1 Level 2 Source temVd • D&D source term evaluation Characterization residual nuclide • Residual nuclide evaluation after decommissioning evaluation Dry decontamination • Unite decontamination using RFC, CCyand plasma Decontamination applicable to highly • In-situ decontamination in the hot cell technologies active radiation • ReusUwaste down-grade decent, after transportation • 3 dimensional laser cutting technology Dismantling and Laser dismantling • mobile remote robots remote operation and remote operation • TRIGA remote metal cutting demonstration Sludge treatment decommissioning • Uranium sludge waste treatment and metallic waste waste mangmnt • Metallic waste reduction and reuse reuse Environment Soil decontamination • Soil waste decontamination restoration and restoration • Site restoration and TRIG demonstration TIOGA • Automatic surface contamination measure equipment decommissioning • RSR under water dismantling equipment Immediate national application field • Mobile remote radiation survey equipment D&D project • Activated graphite treatment TRIGA application • Activated concrete degradation ageing decommissioning • Activated metal degradation by ageing related R&D • TRIGA D/B and computer dismantling simulation
vi The short term R&D is expected not only to apply to the current D&D projects but also to contribute to the national fuel cycle development and also to the technology exports in the future.
V. Proposals for Application The results will be used to establish the national long term R&D planning on 'Decontamination and Decommissioning Technologies'.
CONTENTS
CHAPTER I. INTRODUCTION...... 1
I. Research Background and Former Study ...... 1
II. Objectives and Scope of the Study ...... 3
III. Contents of the Study ...... 5
1. Evaluation of D&D technologies and their demands...... 5 2. Evaluation of technology demands in Korea ...... 5 3. Evaluation of prospects of technology development ...... 5
CHAPTER II. PROSPECTS OF D&D MARKET...... 7
I. Prospects of Domestic D&D Market...... 7
1. D&D market in nuclear power plants...... 7 2. D&D market in research reactors and nuclear fuel cycle facilities ••11 3. Comparison between D&D markets...... 18
II. Prospects of Overseas D&D Market...... 20
1. D&D market in nuclear power plants...... 20 2. D&D market in research reactors ...... 25 3. D&D market in nuclear fuel cycle facilities and their sites...... 27 4. Comparison between D&D markets...... 38
CHAPTER IE. EVALUATION OF DOMESTIC D&D TECHNOLOGY DEMANDS AND THEIR LEVEL...... 41
I. D&D Target Facilities and Degree of D&D Technology Difficulties •••■41 1. D&D Target facilities...... 41 2. Degree of technology difficulties according to D&D target facilities.... 41
II. Necessary D&D Technologies and Their Level in Korea ...... 45
IX 1. Evaluation of technology tree and the technology level...... 45 2. Necessary technologies according to target facilities and their level.... 61
CHAPTER IV. EVALUATION OF SHORT TERM R&D TECHNOLOGIES QND&D...... •'...... 67
I. Evaluation of R&D Goals ...... 67
1. Evaluation of final R&D goals ...... - 67 2. Evaluation of stepwise R&D goals ...... 68
II. Evaluation of Detailed R&D Items and Their Technology Level...... 69
1. Evaluation of detailed R&D contents ...... 69 2. Evaluation of technology level according to detailed R&D items •••••70
III. Analysis of Technology Development Program and Achievements-77
1. Technology development program ...... 77 2. Expected results and proposals for application ...... 80
CHAPTER V. CONCLUSION...... 83
REFERENCES...... 85
ANNEX I. D&D TECHNOLOGY TREE AND THE CURRENT STATUS OF THE TECHNOLOGIES...... 87
ANNEX R DOMESTIC TECHNOLOGY LEVEL AND APPLICABILITY OF DETAILED D&D TECHNOLOGIES...... 89 s n
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(3) 4)4 44 4)5 4# 4#r425 #454 #454# 4 4- 44444 licence4 #4-3 44 44 #4# 4 444 4* *#, WWER 44 LWGR4 #454 #4#4# 4 20-30444# 44 4 4)5*4 PWR4 BWR# 4044 *454* 3m4#4[2.6]. #7D #44425 34# 5 $1* #454 4 70%7} 453444# 4445 544 30# *# 4## # 455 44 #23.5 44 44 #454 44# 4454 444 5 # 4 #44444 4#44# 44 44 30425 7M4424, #45 3 4 4 3)3)4## 304431* *43 200 M$5 444 4## 4#45& 4[2.7], 4)4 444 #45 4)4 54 4#4 4)3) 44# 44* 2 2.124 44444. 20104444 #44 45,800 M$, 20254444 444 * 87,400 M$4 4#4 5## 425 44# 5 $14. 2# 2000 - 2010 #4 3)30 527} 37j) #7}42 2010 - 202043) 3)3) 527} 7}# ## # 425 3)4# 5 $14. -22- & 2.ii 4=f #4) 4-71 4-4 4ir 47) 44471 £44 -J; 7} V- vj 44 Vl-r -71 4-'--4 4-v- 4 4 471 443 443 (48.544) 4X8.544) • 7147} 44 4 7>444 . 444 4-n-3 &4 16 9 204 9 7}444 • t>4 43 4tiD4 "7147} ?14 f- 7l^#4 59 10 20^d 10 • 4 4 #14 4 4 4 • 444 443. 44 #4 20 16 124 1 44 • 44 #4 414" "71471 44 4 7l^-#%j 714: 54 1 194 1 - #4 4)4 44)4 - 4"4 44 4# 5-i 4 »> 29 4 204 4 . 4^ 4^^ • 444 44-3 44 #4) 3$) Til 12 1 104 1 44 - 44 4^4 4-as} 16 1 - — - 44 44 44= 44 • 44 444 44 35 10 234 9 »4^444- 44= -4-4 44 4)4 - 7147} 44: f 7}^#4 " 444 443 44- 37] 44 107 19 184 14 7}^#m ^ ^4- 44 44" 34 ♦ #4 4)4 444 184 Total 348 71 49 (4^) -23 - & 2.12 44 #3^4 44 f A/f3 33 (44 = M$) 3-V- 43 44 3433 4 3 43 34 2001 64 12,800 2005 145 29,000 2010 229 45,800 2015 366 73,200 2020 413 82,600 2025 437 87,400 4. a# €4 432^ 4 44 44 • 41 44 4^& 44 444 #3^4 414 44^ 7}^ ? 444 4)4 ^4 4 444 47RPSR)4 ICRP 604-#-4-4 44 ^ 444] 4)4 444 4 3#4 44 ^4 #43, RCP, 4343, 3 3343 f343 34- NSSS 44 33 5)^4. 4# 3 44 33^ ^ 4^4 44 4444 4)&44 3343^-& 4 4]# 44, 33 M3 4^34 4, # RCP 44# 4444 44 444 44 433&* 44444. 44334- 433 444 44 - 44 44 4# 33°-S 444E2.1- 2.31 RCP 444 33M3 3# 444 333 103, 4 4# 443 2033 33^.0)-^%, RCP, 33M3 3# # 3 4344 ^A433 44 1.0 M$, 3.0 M$, 10.0 M$o.& 44^-4, 4 4#4 4 4 34 204 37] 3-7] 4A4 50%* 7}344 conservadve#4 47}444. 4 34 # & 2.134 34444. 4 3&34 2005434 €3 33 -^.3 43 44 4-S.7> 7>4 #444 34 43 - a3 33 44 3 3 4344 43-4 344 4 50% 43-3: 4333- 3 4" 44. -24 31 2.13 €4 943.4 ^ 4^^9 xiM - a# 4449 (^4 = M$) 9 '1 M4 #4)^ 4 4 RCV 4 4 . 4i 44 4 3 #9 44 #3 44 #3 '■ -: 49 49 49 49 H] -g- 49 2005 1,370 1,370 483 483 161 161 2010 470 1,840 141 624 47 208 2015 240 2,080 72 696 24 232 2020 - 2,080 - 696 - 232 2025 - 2,080 - 696 - 232 4449 4 2,080 696 232 2. sflsq <29^ • sfl^l x\% 7}. 99 1998# 9 #94 # 47744 #9^7} # 4443.&#^44 4 9 2627)7} 9#94 jz. 21544 #939 7}944 4# 0.4, 137)4 #95. 7> #4) ##43 #4-[2.6]. #934 #;e# 9% n# 2.54 444# 4. 4 3# 4)4 394 7}9 # #939 #3 94# 44, 7}9 444 #939 70#494 47#M 44 97}a}4, #4) #93 4* 444 #7} 44* 4443. %M. *4 9# 49-3.4 3|5- 7}94 44 & 2.144 44-444-. 4 93 *4 7}99# ^ 78%4 44-4* 20347} 7}9# 4 204 4# 4 #3#, 59% (1544)9 304 49 ?}94#3 404 49 7}94 #933 264(io%)4 ^9 # 4 $14. -25- A jo, A W|o ,2. 2. A ru A Hu A A A HM A A Number of RR A A DO Hu A Hu nr I—* no H4 Ol 1 A A >4 A -U to A ojW A Hu k r 0 1 |M Hu y a 0 Hu A A 0 A - V - k A A f- A 1 1 1 8 HJ Ini W A A tnj 0 2 0 1 8 0 5 )'V-1 A A 4^ A A A Xi Vi W A ( A oh dS, in? A 4-J A A _aL to Hu oh JdL § to A k= Ox A XI o[n o. X ' A A ojo r|r A A N a A dp A R> DO ■ Hu Hu 8 2 1 rjo 1 t—1 - Hu O) A A DO CO A to A A cn ►tx CD VV #' a A 4> M A A A # ojo ohl A r$ a A A it A 4> A A o|t> 08, A lujo A A A A A m A 4> A M, A Oil a 2.15 31M #4^4 #4 4-8-43 #4 (##: M$) #.% Qll 3 3] 3 43 7] 4 4 3 4# 44 2000 154 896 2010 203 1,181 2020 237 1,378 2025 249 1,448 3 #444 #4&4 4# - 44 334%# 4#37] #3 4&&4 a 2.164 4#3# #e #4&4 ##3# 44%% #4 5 MWt #3 %% 4## #4%4 %#3 #4%* 433#%, 5 MW# 3# 4#M #4%4 314444 44 3- 1.22 M$, 5 MW %3 e %#4 #45-4 444 24.20 M$% 333#3[2.8-2.9]. 2010#444 #44 %%# 4 %% 43-44 44 444 1,181 M$#4 «]4 20254444 34## 1,448 M$4 if%% 43# 4 #4. 3. #44 @9#&44 4# ^ 44 4# - 314 43 33 7}. 434 4M#&44 43 3 44 4# - 314 43 33 (1) 43 DOE4 4^4#&44 4# - 314 3 3443 4-41:2.10] 4% 34444 34## 447] 43 3 #4434 4*3 4#& 44 3# 43# #4 344 37H3-# #%4, 40# #3 4# #7]] 3 a* 43 43 3 43 344 %433- #4 43 443# 4# - 313] 4 3-44344 444 37> 1995#44 433% #3. # 4#4, 1157H^4 site4 43 4# -314 ^ 33434 431 2060# 3 4 434#%% #3343% 230 biDion$7]- %%## 343 44# % 3 3#%& ^4, 43% 4 314 433 #3443% 4#### 44 3%% 3%3% #4 44 e 4# - 314] 3344. -27- & 2.16 431 4^ 43.a=al m 931 y}'s- Vll P T..fi 't! 4-c- /|,UU LV-I; #3) #31 n,c. SDR-SLOWPOK DEMO HEATING PROT 2000 1987 1989 3( ) 7000 10 LUCENS PRESSUTE TUBE 30000 1967 1969 2(1973) 3( ) 1000 245000 40 1324 ARBI REACTOR ARGONAUT 10 1962 1975 3( ) 1 JEEP II TANK 2000 1966 2(des.) 5106 EWA TANK WWR 10000 1958 1( ) 1800 THAR ARGONAUT 10 1974 1991 3( ) 5000 AFNEC TANK 10000 1965 1970 1(1971) 3( ) 42200 30 -M4I RRRCREFERENCE RES TRIGA 1000 1967 3(2007) 850 26000 55500 55500 160 183 2545 RTRCREFERENCE TES TANK 60000 1961 1973 1(1973) 3(2001) 15600 464000 13653000 13653000 4933 3220 CP-5, ARGONNE NATI HEAVY WATER 5000 1954 1979 1(1979) 3(des.) 12100 31820000 500 210 AFRRI TRIGA RESEA TRIGA MARK F 1000 1962 3( ) 3758 60000 181 HEIR TANK 85000 1965 3(des.) 20000 ORR, OAK RIDGE TANK IN POOL 30000 1958 1987 3(des.) 6000 NRX REACTOR HEAVY WATER 42000 1947 1992 2(2002) 30000 700000 2500 WR-1 HEAVY WATER 60000 130000 1000000 1000 103 1965 1985 2(1995) 6800 STAGE FR-2 TANK 44000 1981 50000 120000 7000000 1300 1961 2(1996) 230000 Z Xu MZFR HEAVY WATER 200000 1965 1984 10000000 3(2001) 143000 7120 STAGE JEN-1 MOD POOL 76700 3000 1958 1984 1(1992) 2( ) 2560 96200000 36 325 RAPSODIE FAST POWER 40000 1967 1983 3(1992) 25000 80 2545 GLEEP GRAPHITE 50 1947 1990 1(1994) 2(1996) 15500 40000 1480000 150 100 PLUTO HEAVY WATER 26000 1957 1990 1(1993) 2(1994) 15500 120000 265 150 100 M' 4# 34 ^4^ 44# >-!* iM #3) ##### T 4 Man- U] j1 ### ill! 4^ Cd) (\3) Ills GBq GBq m3 mSv DIDO HEAVY WATER 26000 1956 1990 1(1993) 2(1994) 15500 120000 7326000 265 150 100 THE UNIV RESEARCH ARGONAUT 300 1964 1991 2(1992) 3(1994) 2500 4463 2094 4662 192 63.7 STAGE WINDSCALE AGR GRAPHITE AGR 120000 1962 1981 2(1993) 3(2008) 67000 2 Sc CEER POOL 1000 1961 1975 3(1986) 1500 1110 5 STAGE NDTF LIQUID METAL COOL 50 1961 1971 3( ) 3000 510 3S3. EBWR BWR 100000 1958 1967 1(1967) 3( ) 14000 CINTICHEM NUCL RE POOL 5000 1961 1990 3( ) 155215 3600 3660 BORAX-5 EXPERIMENTAL 20000 1962 1964 1(1989) 3(1993) 367 4 # 44 site # Hanford Site, Savannah River Site, Rocky Flats Environmental Tech. Site, Oak Ridge Reservation, Idaho National Eng. Lab. #4) 57% site?} 34 ^3-43-# 4 60%# 333-^ 44 site 44. 347]# #3, #343, 4# 4 43# #4# zisja. ^ A site # 34 43:4 #44 & 2.174 3 #434. ^4 Site 1 43 • 44 43444 #h#-4 a 2.184 44434. & 217 44 DOE# M43&^7] 3^ g 4-3 43-44'#34#x}^ D&D • Back-end Nuclear Fuel Cycle / Defense Related project 43" Facilities & R&D Lab Project •434-44 #-S-4 site 4 ■ 115 (3500 4# #4) 43- • ^.3 site# 80%4 2035444 #344 43 • 4443- (1995-20604) : 170-330 billion U$ (#44 = 230 billion U$) - 1998 : 6,014M U$ - 1999 '• 6,500M U$ for 30 projects Project %■ • 4 44A 44 (billion U$) 44 ^ - Waste management : 112 (48%) 28J1 44 - Environmental restoration : 65 (28%) - Nuclear material and facility stabilization : 22 (10%) - National program management and planning : 19 (8%) - Technology development : 12 (6%) • Hanford Site : 21, Project • Savannah River Site : 21 site# 44 • Rocky Flats Environmental Tech. Site •' 10 344(%) • Oak Ridge Reservation : 10, • Idaho National Eng. Lab. : 8 — 31 — a. 2.18 44 DOE 4 4^ 4m4 ea Site # 43 • a# 43 4^ Site 43 44 43 44 • Reactors ' PUREX / Processing building Handford Site • 200 Area • Ground Water • Canyons Savannah River Site • Reactors • Ground Water • Pit 9 & Buried Waste at Radioactive Idaho National Eng. Waste Laboratory Management Complex • Idaho Chemical Processing Complex • Gaseous Diffusion Plants Oak Ridge • Off-site Program Reservation - Y-12 Rocky Flats • 881 Hillside Environmental • Solar Ponds Technology Site (2) 444 43 -44 4 - #4 44 4^-4 ^^43&m7) 4344 #'#71 444 4# 57i| ea Sites4 44 Sites 4 43 - 44 44# 44 & 2.194 a 2.204 444 4 44434-. 4&44 20104444 4444 4s.a 61 billion $34 44 4444it2.^ 131 billions #2.& 4# e if&4 444# 4 4 $14. -32- & 2.19 444 57% 44" ^44 44 . a# 4^3 (44 : M$) 2001 2006 2011 2016 2021 Site - 2005 - 2010 - 2015 - 2020 - 2025 Hanford Site 9,604 8,709 8,044 7,158 8,182 Savannah River 7,496 8,750 7,330 8,038 6,717 INEL 2,808 3,110 2,828 2,866 2,679 Oak Ridge Reservation 1,935 1,798 1,803 1,527 1,161 Rocky Flats 2,721 3,764 2,587 2,169 2,693 & 2.20 44# 444 4^^4&e4 a,]g 44^3. (44 : billions $) 2001 2006 2011 2016 2021 Site 44 - 2005 - 2010 - 2015 - 2020 - 2025 571] 4-3. Sites 25 26 23 22 21 44 Sites 6 4 2 1 1 4 31 30 25 23 22 4. 4Til 444 @M&^r7l 44 44 - -gfl^fl a} 4 44 4^1 4444 4^11 7H44&44, 4^#444, 444 #a4 44 &^4 444 44 -44 4% & 2.214 4#444. 4# 4a^ 7i7H 4^741^440] s-4«t- ^-4 4 3.444 4 44844 4^4 4^-44 a4ea. $14. & 2.2144 847H 4#4 aa4^.7} 5E444 $144 ^4& 44 4444 7}^ ^44 444 444 4 1907^4 4^.4 4^-^ a 3.4^ $14. -33- & 2.21 41314^ 3933-^7] 4 #*3 4#44 *4 No. 7l# Tt* »3. ?*** «*4 % 71* *4 z4 4#^ (m’) (m1) (mo (M-mSv) 471# 1 DECONTAMINATION FACILITY, 1960s 1961 UK 800 6400 44*& 3(1983) e 5 300 0.19 W1983 Sellafield 2 KARLSRUHE 44*14# (WAK) 1971 1990 5W cell GER 126m" *94? 3(2004) 30.5 12,700 Only off-gas cell 3 CHEMPROC.CELL.WEST VALLEY 1966 1972 SI’S! cell USA 2440m’ 44? 3(1996) 4 RADIGCHEM HOT CELL HANFORD 1945 1987 £W cell USA 100m! 44*5 2(1993) 5 FIVER PROTOTYPE VITRIFICATION 19691981 FRA 44-8-s. 3(1991) % 50 440 230 8.19 M$, only eqpt dismantled 6 GULLIVER 1965 1967 -frzlZ* ERA 4 4 @5. 3(1986) 12C 7.5 7 ESTER MINI PILOT PLANT 19631964 ITA 44? 3(1986) 7 8 Pu FINISHING LINE 3 (B-209), 1963 1987 UK 100m’ 100 300 44? 1(1996) 2(1999) 84 33 660 450 14.76 M$*996 SELLAFIELD 9 Pu FINISHING LINE 4&5 1960s ** UK 44 39^ M$*988, still oprating 10 APOLLO 1950s 1983 ** USA 360tHM/a 44*5. 2(1996) 36 290 1%800 11 BLDG C. LYNCHBURG TECH CENTER ** USA 44*5 3(1994) 10 12 CAFEHURST 7>>*?#-;8 1953 1982 UK 350kSWU/a 150,000 1500,000 44*5 3(1996) 16C 1070 216 600 133 W1995 13 OAK RIDGE 1945 1985 USA 7700kSWU/a m 3(2010) 910112 14 GAS. DIFF. PLANT. PADUCAH 1954 1990 SRI'S) USA m 15 GAS. DIFF. PLANT. PORTSMOUTH 1960s 1990 USA 7900kSWU/a m 3(2000) 16 VAUNDABD Z-FLANT enrichment- SAP 300kSWU/a 44 helicon 17 NUKEM-ALT FUEL (U,Th) FAB. 19601988 7}# GER lOOtHM/a 2(1996) 3(1998) 1C 2400 1000 100 PLANT. HANAU 18 HOBEG 4*57|-g-#*- HANAU 1972 1989 m GER 4tHM/a 3000 16,000 44? 2(1996) 3(1996) 72 300 300 50 19 SIEMENS BRENNELEMENTW.HANAU 1996 GER 750tHM/a 44 20 IPU PLANT, ACSACCIA 1971 1987 yys- ITA 0.9 44? 2(1997) 21 IFEC PLANT 1965 1990 7R ITA 6000m’ 44*5 3(1993) 300 22 B-227 FR FUEL FROD.PLANT 1970 1988 m UK 30G6 30250 44? 1(1986) 2(1999) 72 47.5 170 960 16.8 M$ to Stage SELLAFIELD 2*996 MM MM *4 3*1 No. 4M ** ?7l *?*41 7l* #3. W (m1) M4 (MY) (M-mSv) 471* 23 COPRFEIP. PLANT.SELLAFTELD 1969 1976 7l? UK 30m" 320 1400 *1*1*5 2(1990) 60 7.5 261 39 3.39 MS/1990 71? 24 DRY RECOVERY FLANTSELLAHELD 1974 1975 UK 100 400 2(1982) 10 2 16u6 31 80MS199B 25 LANL TA-21 BLDGS3 & 4 SOUTH 1950s 1984 71? USA 1000m’ 1000 *1*1? 3(1995) 26 EERNALD 1952 1989 71? USA *1*1? 2(2010) 192 27 CIMARRON 1967 1986 71? USA 2400m' *1*fl*s 2(1991) 108 700 7000 28 LOS ALAMOS W Pu M 1944 1978 71? USA 5330m’ suites. 2(1981) 36 29 DEPLANTED U FACILITY, COMRTON 1967 1986 71? USA 5800m ’ *1*11*5. 3(1987) 4 30 SPECIAL METALLURGICAL BLDG, 1960 1968 71? USA 2300 *1*1*5 3(1995) 60 MOUND 31 HOT CELL FACILITY, RIS0 1964 1990 Hot cell DEN 17,000m’ 3800 17,000 *1*1*5. 2(1994) 54 34 140 32 OREC-1 FACILITY 1962 1987 Hot cell ITA *1*11*5. 3(1993) 36 20 33 RM2 1967 1983 Hot cell ERA 2800 50,000 *1*11*5. 2(1994) 3(1998) 48 40 300 19.1 MS 34 BAILMENT 18 1968 1995 -MM FRA 10,000 60,000 3(2006) 120 1333 2600 123 MS/1995 35 BLDG B, SITE 2-KRI Ra &Po LAB. 1922 1962 -MM RUS 200m" 480 2880 *1*11*5. 2( ) 8 22 800 80 0.02 MS/1974 36 BLDG 351 HARWELL LABS 1950s 1990 -MM UK 10,351m’ *1*1? 3(1998) 60 191 37 B-229 R&D SELLAFIELD 1951 1995 -MM UK Til SI 2(2044) 500+ 3800 118 MS to Stag©/ 2/1998. ' phaed shutdown to 2010 38 VARIABLE ENERGY CYCLOTRON, 1960s 1991 -MM UK 11m’ *1*1*5. 3(1994) 12 HARWELL 39 ANL EAST FACILITIES -MM USA *1*1? 3(1986) 680 40 GE-AFL, VALLECITOS, 1962 1979 -MM USA 375m' *1*1*5. 3(1982) 42 488 41 NUCLMAT.DEV.BLDG 055,SANTA 1964 1980 -MM USA 1100m’ 1100 *1*1*5 3(1986) 42 109 SUSANA 42 Pu FAB. FAC. BLDG 350 ANL 1959 1973 -MM USA *1*1*5. 3(1963) 48 60 545 43 WARD LABS 1966 1979 -MM USA *1*1*5 3(1982) 36 470 44 TUNNEY'S PASTURE 1952 1984 source CAN 3000m’ *1*1*5 3(1994) 48 8.6 MS-1991 45 ELAN DB 1970 1973 source FRA 3840 15,400 *1*1? 3(1999) 180 88 1300 360 59 MS/1990 46 1968 1970 source FRA 200 800 *1*1*5 3(1994) 60 10 1500 590 ELAN HA 4# 6.8 MS/1994 4^44 114 4# No. 71* 7]# #3. 44N 34 (m‘) (nf) (MY) (M-mSv) 44* 47 CAESIUM EXTRACTION PLANT, 1965 1968 source^-ti* UK 400m' 400 1600 *54# 2(2000) 120 50 193 31 MS/1994 SELLAFIELD 48 Pu-238 FACILITY, SAVANNAH RIVER 1963 1984 sourced-tb USA 500m' 44# 1(1989) 60 250 49 Sr SEMI WORKS PILOT FUEL REP, 1949 1983 source'll! USA 1500m’ 44# 1(1989) 6 110- HANFORD 210 50 FISSION PRODUCT PILOT PLANT 1948 1970s source48-i+ USA 44 25 51 MAIN BLDG EUROCHEMC 1966 1975 BEL GOtHWa 15,120 56,000 44# 3(2004) 132 400 2785 82 MS/1998 52 FINAL PROD. STOAGE BLDG 1966 1974 71144 BEL 3290m' 44#s 3( ) 20 13a 7 2.1 MS/1998 EUROCHEMIC 53 REPROC. PILOT PLANT, GANSU 1960s 1980s 7fl44 CPR O.ltHM/a 44# 3(2013) 228 54 EEFROC. FACILITY ATI 1969 1979 444 FRA 0.2tHM/a 1320 15#0 44# 2(1994) 3(1999) 156 160 650 2700 31.4 MS/1989 55 REPROC. WORKSHOP - BLDG 211, 1963 1994 444 ERA 5tHM/a 44# 3(2008) 120 4020 2000 12300 137 M$/1994 MARCOULE 56 CELL 82, MARCOULE 1960 1982 444 ERA 5tHM/a 44*& 3(1993) 6 Purif cell, 200g Pa PILOT PLANT 57 ATTILA 1968 1975 444 FRA 250m’ 10,000 50,000 44#s 3(1987) 44 31 525 232 273 rnises 58 UPI, MARCOULE 444 ERA 400tHWa 10,000 50,000 44 3( ) 500 18,000 16,659 Dismantling to begin in 2010 59 KARLSRUHE REPROC. PLANT (WAK) 1971 1990 444 GER 40tHM/a 44# 3(2005) 180 1200 1600 8625 1181 M$/1995 60 WIEDERAUFARBEITUNGSANLAGE, 1971 1990 444 OR 40tHM/a 44#a 3( ) 19 125 200 7 92 M% Off-gas KARLSRUHE cell 61 P.P. TROMBAY 1966 444 IND 44€5. 2(1977) 36 4 30,000 890 Plant refurbished and in operation 62 JAERI REPROC. TEST FACILITY 1968 1969 444 JEN (point) 3560 18,700 44# 3(2004) 108 147 1600 17200 76.5 m NOR 44€a 2-3(199 63 REPROC. PILOT PLANT, IFE,KJELLER 1961 1968 444 0.2tHM/a 300 2800 5) 60 13 50 30 0.66 M$ 64 B-205 REPROC. PILOT PLANT, 1956 1968 444 UK 800 2(1999) 72 90 6.34 m to Stage SELLAFIELD 2/1994 65 B-207 URANIUM PURIF. PLANT 1952 1973 444 UK 1000 20,000 1(1995) 2(1999) 60 25 500 20.7 M$/1996( only, partially shut down 66 B-206 SOLVENT RECOVERY PLANT, 1962 1963 444 UK 75 600 2(1989) 84 33 425 2&1 MM994, only SELLAFIELD partially shut down 67 B-203 Pu RES.REOVERY PLANT 1964 1986 444 UK 400 12,000 44# 1(1995) 2(2008) 168 105 26.6 MS/1995, shut SELLAFIELD down 68 B-204 REPROC. PLANT, SELLAFIELD 1962 1973 444 UK 1575 96,000 44# 2(2010) 230 1400 900 1225 MS/1996 4**2) 4*43 °]S] ** 34 No. 71* 4M ** *7> *3. % 4* #3 -483 (m‘) (m-) (WY) (M-mSv) 44* 7plEl FRA 58 UPI, MARCOULE 400tHM/a 10,000 50,000 3( ) 500 18,000 16659 Dismantling to begin in 2010 m 69 THORP. SELLAFIELD 1994 UK 1200tHM/a 596 MB/1998 operating facility 70 B-205 MAGNOX REPROC.PLANT 1964 2007 UK ISOOtHMZa 15,670 175,500 TIM 2(2021) 168 2040 4050 69.3 MB to Stag 2Z1994,stil operating 71 NORTH GROUP, SELLAFIELD 1953 1985 443 UK 1500m’ 1500 7500 44*5- 2(1990) 10 22 m/1990, unirradiated U 72 WEST VALLEY DEMONSTRATION 1966 1972 USA SOOtHM/a 44* 3(2024) 360 24860 Demonstration project FROJECCT 73 B-29 FUEL HANDLING PLANT, 1962 1964 **SF4* UK 5000 30,000 2(2010) 156 104 1100 47.2 MB to Stage 2/1994 SELLAFIELD 74 N FUEL STORAGE BASIN, HANFORD 1963 "MSF4* USA 6000m’ m 2(2010) 9000 Stabilization only sampling 75 B-205 Pii CORRIDORS. SEELAF1ELD 1964 1968 area UK 44*5. 2(1996) 70 35 20 110 4.0 m/1991 76 B-30 POND, SELLAFIELD 1960 1986 SF4* UK ISOOtHMZa 5200 40,000 44* 2(2019) 168 4450 472 m/1994 m 77 B-311 FUEL HANDLING PLANT. SET)* UK 14,400m' 14,400 207 M&/1996 still SELLAFIELD operating 78 FRA refurbished 2(1998) LIQUID WASTE TREATMENT and still Refurbished and still STATION, MARCUOLE operating operating 34171*7-)* 79 B-31 SLUDGE SETTLING TANK, UK 2(1998) 36 7.4 m/1992 to Stzye 2 SELLAFIELD 80 B-41SILO,SELLAFIELD 44*71* UK 44* 2(2028) 60 1100 81 NIAGARA FALLS STORSGE SITE 471*7)* USA 44* 2(1997) 82 B-136 (MLW&HLW) 1996 2065 471*7)* BEL 1208m ’ ti* 3(2070) 60 400 83 B-151 (LLW) 1988 2045 471*4* BEL 13,900m ’ ** 3(2060) 27 42 84 ON-SHORE AND OFF-SHORE SEA 1967 1982 471*7)* FRA 2400m 44*5. 3(1992) 60 513 1567 Total waste activity DISCHARGE PIPES only phases 1&2: 6976 GBq 4. 444 43 - #4 343 43" 3a 37)144 43# 20103443 343- 20253443 44 & 4f3 443& 44# 3^434. 7% 2010344 3444 3 a 19983 4344 3 444^-& 7>^343 443 343 44f, 34a. ^ ^3af4 44 4 7}4 44 if2.7} e 343 fM3a. f4 43# 442.2. 444 43-414 44# f443 44#&3 3 3 4iJl 3#4 4# 3## ^-3 2.64 34334. 3 #4a.43 20103443 4 4 432.3 4 110 billion$3 42-3 3, 33a.f4 f 2.(61 biUion$)7} 343 56%* 4443 -34-3 44 & 4 4f 2. 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RCP iW# ^ ^^7)1# #3./HM4, 1998. 2.2. Back-calculating the Cost Effectiveness of Steam Generator Channel Head Decontamination at Beaver Valley Unit #1, in EPRI Radiation Field Control Seminar, 1995. 2.3. C. A Bergmann, "Evaluation of PWR Radiation Fields: 1991-1996", EPRI-TR-107566 (1997). 2.4. 7}^ f A ^ KAERI/AR-581/2000 (2000). 2.5. BNFL, "Back end fuel cycle strategy study for the Republic of Korea", 1994. 2.6. Joint NEA/LAEA/EC Workshop on Regulatory Aspects of Decom missioning, Rome, Italy, May, 1999. 2.7. OECD/NEA, Decommissioning of Nuclear Facilities: Analysis of the Variability of Decommissioning Cost Estimates, 1991. 2.8. International Atomic Energy Agency, "Decommissioning Techniques for Research Reactors", Technical Report Series No. 373, IAEA, Vienna (1994). 2.9. G. J. Konzek, "Technology, Safety and Costs of Decommissioning Reference Nuclear Research and Test Reactors", NUREG/CR-1756 (1983). 2.10. 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Kaiser, C. E. Benson, E. S. Meyers, V. C. A. Vaughen, "Decontamination by cleaning with fluorocarbon surfactant solutions", ORNL/TM-12444 (1994). [2] "#T4M4##7l 71)^4 4#4 #444 4444 4##A 4 4#44", KAERI/AR-581/2000(2000). [3] Oak Ridge National Laboratory, "Technology Logic Diagram (TLD),"K-2073, February 1993. [4] C.A.Foster, "Solid Deuterium Centrifuge Pellet Injector," J.Vac.Sci. Tech., Al(2) 952-958, 1983 [5] C.A.Foster, "Surface Impact Cleaning by High-Speed Cryogenic Pellets," Second International Workshop on Solvent Substitution, Phoenix, Ariz., December 10-13, 1991 [6] R.J.Dabolt, "Evaluation of Pelletized Carbon Dioxide as a Fluidized —115 — Abrasive Agent for Removal of Radioactive Contamination," Document No. ER-89-002 (1989), Chem - Nuclear System, 220 Stoneridge Dr., Colombia, SC 29210. [7] D. R. Linger, "Fundamental of dry ice blast cleaning technology" 1997 precision Cleaning conference, May 30, 1999 (1999). [8] J. G. MALM, P. G. ELLER, and L. B. ASPREY, "Low Temperature Synthesis of Plutonium Hexafluoride Using Dioxegen Difluoride", J. Am. Chem. Soc., 106, 2726(1984) [9] E. B. MONDAY and D. W. SIMMONS, "Feasibility of Gas Phase Decontamination Equipment" K/TCD-1048, Oak Ridge K-25 Site(1993) [10] E. B. MONDAY, "Preconceptual Design of the Gas-Phase Decontamination Demonstration Cart" K/TCD-1076, Oak Ridge K-25 Site(1993) [11] R. L. FARRAR, Jr., "Safe Handling of Chlorine Trifluoride and the Chemistry of the Chlorine Oxides and Oxyfluorides" K-1416, Oak Ridge Gaseous Diffusion Plant(1979) [12] R. L. FARRAR, Jr. and E. J. BARBER,, "Some Considerations in the Handling of Fluorine and the Chlorine Fluorides" K/ET-252, Oak Ridge Gaseous Diffusion Plant(1979) [13] K. TATENUMA, "Newly Developed Decontamination Technology for Non-Incinerable Radioactive Waste Based on Gaseous Reaction of Carbonylation and Fluorination" Proc. Waste Management 96, Tucson, Arizona, February 25-29, 1996. [14] K. TATENUMA, Y. HISHINUMA, and S. TOMATSURI, "Developmental Study of Gaseous Decontamination Technology Using Carbonylation and Fluorination" presented at Annual Mtg. Atomic Energy Society of Japan(1995~1998) (in Japanese) [15] N. WATANABE et al., "Fluorine Chemistry and Industry" —116 — Kagaku Kougyosya, 160(1973) (in Japanese) [16] N. ISHIKAWA and Y. KOBAYASHI, Fluorine Compounds, 6th ed., p. 52, Kodansha-Scientific (1989) (in Japanese) [17] %4€44%% A% 4 (042-868-2753) [18] %44%m 444#44 4## L-K ^L-H Si @7[ 1) 44 7]#%# ‘83% #E] ‘98% 44 KAERI44 4% 4 #?]]%# 4### ^4 44440]^^, %%4%# 4% A4## 4%AS ^ 4 °1%%%A snow^-x[Tg_ sand blasting #4 41% 7]% 7] #7]] #4 4%%%4. 4%%%A snow44%# %£4 %4% ti]Jl%xj ■$_<$%. %47]#S %4SDI4 K.C.Tech.44 ^]7j]# ^ 4 #4# # 4%%3l %A% %%-% #44 a)-g- #4^ &%. -^4] 4%%Y1!M4 %xJ%#4A #4AS C02 Snow44%Y * 4S%4A4 %X}4#% %% ^ 31%4 4 % 4 % 444^ 5 %%4 %-§-%» #%%4. 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(ARU44 44 #4#4 4A4, 44#44# #*}4 4444 4444# 444 # 4#4 44. 3144 44 444 44 4444 %M 4#44, 44 7>4 44# As 444 444 444 44 - 4 44 4# 7}#4 5)144 4444s# Diode-pimped YAG, Diode array, Macrowave pumped C02 4 4 4 4444 44 5) Science and Technology 7fl4 -HA# - 44 44 SNL 4 44 4 #4# 51147-1 ## 4# 444 44, 444 44 ^ S114H1# 44 ## gantry 444 4# ##4-s 4444 #414 414 ^ 441# 44 444# 4#44 #44, &4, #4s 44 # #44 44# #4# 4 4# #47} 444 4A4 Mockup 4 #4 44# # 4 4# 444. -135- - *3M4 44 4 #31 4#* *4# 4* SNL 54- 4*4 & ## *##4 ** 4*7} *2#. - 447-1 4* *#*4* 44: 4444 *44 t11 *# #4 44 44 7l#o] #_&# - 444 44 focus 44 4*# 4* *44 end-effector# 4-# *2 44 ^4£7> *444 54 4? 42# 4# 5-44 * 2*. #4, 444 441-4 44, 44 *5 4-444 44#4 4444 44 444 44 4-4*44 #44# #4# * 44 44 444 ^#4 €-8.#. - 4144 444 44# 444 4#44 444# #4 4**4 #4- 4# 4# ^ 4*4 444* *4 44# &44 44444 44 5444 44 4*4 * 24-. - *4 444*5* 31*4 3144 44* 4* 4* 4 3144 4 444 431 44 4 44 4*4 #-8-4-4, - 44*4 444*5-# #4451 44# 4* 4 555 4* 4 *4 *-8-4. 6) 4*4 4-44-4 *-8.4 4# - 44 4*43-1 s 4*444 4## 44 4#* *4*42-5. 4 44-4# 44 4314 44 #244, - 4*44 44# 44 KAERI 2# 4*4 7fl* 4 44444 4 57> 424. - 7H4# 2*4*4 4431 4*44 4 4*44 4* ** *4 4 44 4*44 #41* 4-#4 4144-4 44 #44 443144 4* 4 #4 #2#. -136- 7) ^ - ^ ^f^(KAERI) : (042-868-2753), (042-868-2913) - KAIST : ^^-9- (M^^-^4) - Sandia 71T4: : Randy Mckee (505-844-9600) - E|^- BNL ^5L4i : Paul Moskowitz ( 516-344-5062), Paul Kalb (516-344-7644) - t3!^" Schafer Corp. : Robert F. Walter (505-242-9992), Marc Hallada (505-242-9992) - Marc R. Hallada, CHEMICAL OXYGEN-IODINE LASER FOR D&D OF NUCLEAR FACILITIES, Proceedings of Second Topical Meeting on Decontamination, - Decommissioning and Reutilization of Commercial and Government Facilities, Knoxville, Tennessee, September 12-16, 1999. (ANS Order # 700269, ISBN: 0-89448-645-4) - -S-vt]] o] x] (www.perceptron.com ) -137- 4. ^4 S! 1) #4) 7]#%^- - 4-A4 44 4 4# 44# 4445 5)) 0)7)* 4-0-# 4 #4 1 #444. #4 445 A444444 ^ 7^71 #^r 4# 44 $H4 #4 ^24 A4#44 AP0i: 45## # $14. 5)147)* o)^ 44 44 4 7}*7)*5 3.711 511 4 Tl 444, 444 444 4544 4 44 7}#4e^ 3 4#5 4# 4 44. - 4.7)) 44 7}-o--S- 4 4 444 454 71-44 5)) o )4 445.4 Nd:YAG 4447} $14. 444 1.06um4 Nd:YAG 511444 44444 4 2 kw 444 444 71-445, 44444 4 4 kW 4^4 5)144447} 44445 $14. 47H 4 7} 4 "gY-5444 4= 2 kw #4 4# #4 44 4* 441444 5#A& 7l)#4^A4, 1-24 ^4 4^ ###7} 4 #4 45 $14. 44 444 1.3 um4 COIL Z11444 44 44 7)14 444 $1 54, 44 4 444 44 447} 4= 10444 4 4-4 7}# -444 5)144 44 7) fks. 4544. - 5110)7-1 0)0) 44 4* 4## 444 44- 4#4 441 4-44 44 44- 4444, 44 4444 44 44 4 44 4##A^ 71)7}5)3 $14. 44-rrt- 4-0-4 51144 4# 44=444 47)) 44-4 49-544 4 4 4 ##44 4 6 kW 44, 45445 4 100m 44 454^54, 45 5 cw 4444 4# 4 4 KW 44 45# 444 $14. - 44 44 4 7}* 4454445 51144 44 4# 4 454 51)44 44 54444 #4 444 444. 44 44 4 7}^* 4444 44 444 444 density 447} 1A44, 44 4 7}^=444 4)44 0)4 #44 <94 $1A4, 5)10)7) ** 4 7}^4 #44 5)10)7) 44 34 7)144 $14. 35)3, 44-4 44544 7)144 54 44 4## 44-44 44 7)14 4 4444 447) 4* 138- - 37}# 44* *7}4#*#, KAIST#44 43/71] #4 #7}, 200043*4 #34 yi a}-g-33 #*#7} 4*444-. - #*#7}4##344* 1995444 1997444 *7}# #43 444 *7}* 44 344 ##** 4*71)# 44* 4*944, #4# 44* 3D 444 ##*##4 4 43.4# 7D# 4** 45-43 44. 3# “Anisotropic Laser 3-D measurement apparatus"* 4 44 443 3**3 44. - KAERI 44 4*4 333 ^ 4* 4** #* 3* 4* 7^ 2) 44] 7]*7}#3 - Nd-'YAG 444 **44* 444 *4 4 44 4*4 #* know-how* 43 434, 444 #* #4^1* *3*4 CW *4 444* 7H#* 4*4 $1* *4 #4#44* 4 2kw #4 444* #*# 4*4 $1*. - 3#4 444 *°>* 7}* 10444 44 4 44* 4* 4= 20 kW #4 #44 7}** #*4444 coil* #4 *444 €a>* * 337} * 4* 4 3**3 5134, *4 2.2 kW 444 *4, #4* 4# #*4, #*4* ** 7>4 #4 4#*$a*. *4 3#4 444 444 43# 3* #* **4 4-4*7} 7}** - ##** 4*# 444 44 44 ^ 7}*4 7}**^ * 4* 4 *44* 7}*4 444 *4 7}*# ** 44* 44*44 #4-. *# 4 443* *# 444 *4 34 444 447} * 3*#. - 44-ti 4#3* 4-4 ICALEO '9944 #3# ### 4*7} 4 ** 444 ##44 34 444 4*44* 44 4*4 Heriot-Watt 4 *4- Lumonics 4-7} **33. 44 43# 4** *3*44-. - *A}a #*3* 44 4*7} 4*4 4# *# **7} **44 aj-^-oh* o„i* * 4* 4*# 44- 4 4*4 * 4* 4* 3**3 # -139- -B-. KAERI 7> 5.** 4 O] # 7}* 4 # *4 y-A] 7]#e 4 444 f *4 - *4 7}*#44* *## *44 ## * 7>^-i- #4*4, *4 sfl - ^44 4^4 ** #4 ^ 4* 444 €4 2* 7]#4 *4 7]#& 4#4 7M43 444 43 *#(CCD, 444)* 4444, *4** 44# * 44 4^e4. 3) 4*4*4 7]e7l#4-§-4 4^4 44* #7} - 3] 4 4 444 7]#4 Hacksaw * Plasma Arc 444 4*4 -a# 44 7>4#44* 2 7} 44-, 4x>4a]^=>i] #4471 4# ** 4444 4 4 47M 4* 444- 44* 4# 4*4 4* 24*4 444 *42 *4** ## 4" $14 4*4 ***-442 4#*4. - ^-4, 4441- 44-* 44 *44 4-44* 4144 *4**71- 4* #4 444-2 M? 4 44* *4*4- 4144 4* #2* *47> £.5. *44 244 4-e #24 *7> 4*4 *444 **. - *4442 D&D* NdiYAG 444 *4 ** 4#* 4*4 7>**4, *4* ** 4* #4* *4 444 #4 **4 41 #*4* 2i 44-* *44*4 **7} #3#. — 140 — 2. 7|^7H W- W I-H# 7k &l# 7|#7HW 5^1 4 4 * 4 4 4 44 444# 7^ L-k 441^ ^ MJ§ 1) 1 #31 #S ( 2001 - 2003 ) 4M4M44 44-^1 ^aj- 3144 ^44^ 4^ 7» 2444 4| 4 44 - 44# 4# 511 44 4444 7H# - 51144 44^1 2444 44 444# 7H# - 4#4 ^-Bfl ^j-A] ti ^^oi^i 444^1 >114 4) 44# 44 Jl#4 511 ^14 - 3 KW 444 4 oi 4 4444 44 - 600 urn 4 4-4# 44 44 44 - 444 44 44 444# 7114 4) 3 44 44 #444 - 3 44 4444 44 ;H# - 3 44 444 444 #444 >114 - SIS 44 data 4# 4^-4# 7%# 4) 51147-1 444 manipulator 2#71 # 7H4 - Manipulator 2:4 71 if 7fl4 - 4# 44444 44 4 4 4 manipulator 44 - 4444, 51144 4 manipulator 4 #44 4 44 4444 44 - 14144-44#, 44 4#4#, 44# 4.3 44 #44# 2) 2 441 #& ( 2004 - 2006 ) 4#^ 51144 44 4444 7H4 ^ 44 4# -141 - 7» 7H1: - °1#4 314 • Manipulator 444 °144 3I4 • 44 4 #4# • -3-4# °]^7]^ • 44*4 ^4 4#7l# - 4*4 SIS 44-§- 7,] Zj-^T-X) 44 • ^BJlEll O. ^ -44 €*44# • 4444. 7] ^7^ '*44/444 ^H44# .#4444* 44* ^A]^> ti0U}Al &^7|# 4) 44 #7^ 3L#4 3144 7^ - 4*4 3144 €444 314 - 44 #xM 3144 4^i Ail 3]- 4) 4-0- *€ ^ 7]# ## *4 - 44 4-0-44 - TRIGA 4*444 44 44 44 44 - 7]# ## #4 14. emm lhh ^ s*i 1) &444 4444 - 444 44* 44 4444 ?m " 44 44 : 3 44 • 444 4.4 : +/- 0.3mm • 444 44 : 444 feedback - 44# 44 44 4431 431 4 314 . 44 4431 431 : 44 25 mm 44- — 142 — 2) 343 43 31# 4 444 ~ 34 7}#-§- 31# 4 4 °] 4 ir^ • CW 444 33 : 44 3 kw • 33# 4# : 44 600 um - #43-3- 4# 34 33 • 33# 4# : 431 3 kw, 44 600um •33# 44 : ^1333 9-3^ 3) 3 33 33 #334 - 43#4 34 ^ 33 3## 33 334 3344 34 • #434 : 150x200 mm • 4-413 : 1 mm - 3|4|# 333 334434 33^1 #4 ^ 3^1 • #3 44 : 200 mm • #3 44 : 150 mm • #3 44 : 100 mm " #4 4r^0# : ±1 mm - 4#3 33#4 #Ji4# ;m • -H# 3D camera 4344 34 33 4 ^344 7M • 4144 343 3# #Ji4# 443 •33 data4 4344 ti-4/4#£ S.3 #314# 7fl3 • 33 3# 44 #314# 7m 3 43 - 333 43 data 434 3 4-5.34 5L3.n^) 7113 • 333 data ## 7113 • 333 444 44 33 #314# 7113 • 34-3 ^.43 ^5-n^ 7113 - 44# 7H3 3 43 43 -143 - • ^9 94 3i7] $)- 9 calibration 7] # 7^ 9 .#9 44-4 &9 44 4944 4# #9 995 #4 • #9 94 9 #9 94# 97} • ##4 4# 444 4445. DBASE 44 4) 4 °14 449 manipulator - 44/44 5599 ?H9 • 44 44 49 94 44 •44 442971 9 4^ 494 2:4 44444 9 44 - 44 4949 • 99 4499 ^ 999 2.449 4^494 • 99/714994 4949 4449 4 7H4 94 49 5) 499 592. - 99/44 4-4:719 99 • 44 99 94 44# 44 3 4997} .94^44 4 4#4442:^ 44 4 4997} - 44 99 49 #5 • 94- 9494 4 2.449 94 44 ^ 4997} • 944 4949 44 4997} 6) 49 949 3-#4 444 - 49 94 7}9# 444 99 9459: • 494 99 94 45 59 : 499 45 • 994 449-4 59 = ± 2 5 • 4#9 94 7}^# 94# 94 49 • 4944 94# 9994 49 -144- 7) 44 ^ f 4 - 44 44 44 • TRIGA 44444 ^ 44 44 4111 - 7ie f# f4 3. ^ ^5iy-2>(35i|o|x| l|]sl\) 7k 3# 1E1§ Menipulator L-k 7|#^j ae 1) 44€ ^4 4444 - KAERI 7]- ^.44^1 4444 3 44 44 44 7]^4 3 44 44 (Vision) 4 #4 4444 3 44 444 digital data 44^ 4# ;H4. -145 - - 9971 ^9-711 #7}# 99 A 94# 994## #aq 7H9# ^144 9949 4 #9 #944 #43. 7}994 ^ 947m. 2) 999 manipulator 94 - 94 #42:4 4#9 49444 #94 7fl##A #94 #49 4# 44 ^ 44# 49 #94 49 4944 #414# #9 994## 3.4 9 99 ##7> A##. 99 #4 94 ^4# 7fl#4 #4^4# 4 ## 44 #94 7fl#9 #4# 4#4 #7ii9 aa 4*#A #A4, #4 A449 2:49 9 4# 71-9 #9# 9949# #9A A##. 3) A9#9 7ii9 99 - KAERI 71- A#9 494- 49 9994 94 ^ 2=9 >1144# (4444 2 7H, #444 1 7# #9 44 1 7fl 94 4 4444 1 7H ## 9)9 494-4 994# A# #4 44 ^ 9# 94 94499 /D#. 4) 94999 A#4 444 94 - KAERI 7} A#9# 949 99 1 kW Nd:YAG 444# 4944 #4 444 9# 949 #494, A7}# #99 A#9 444 99# #4 9AA #A. 5) 494 3AA 7fl# - 94#94 949 A#94 9 94449 #494* #9 949 44 4#4 499 3.94#4 7fl#s. #A94, 4# M 49944A 7l#7H9 3=7l 944. 444 #4 A# ^ manipulator# 7fl#9A, 4*9 A## 7H99. 6) 49 #711# a## 444 7H9 - 7H## 944 system 9 #4 Til# system# 4944 9##9 146- #^# 4^4n, 33 #44 34 ### 44 333 system# #3 7)1###. 4. 4 s 431 ^ 4m <4 isi^ei- - KAERI 7} s##4 434 34 n#3 443 433#, #3 s# ^ sss 3# g 444 33 #3 34 43 334 433 KAERI 7} 4E3ns. #3. - 3 44 34 #3data # °144 manipulator 3 3=44 444334 44 433 ^ 433 3#444 344 #444 34. - 333 4433 34 4s 4#4 444334 3 3#4 iL#4n 44 34 Sandia 34S44 4 44 43 3#4 7fl4. - 333 444 Ji»4 3334 34 44344 43 43 4333 3 3444 Ji44 Nd=YAG 333# 3^43, 433 344 n43 jl 4# 333# 4344 444 4444. -443 43-7] 43 434*3# 443 434 3## 44s 434 3 3#4 43^/43-4 433 4# 3#7>4n, 443 #3-3 3443 #33^. 3#3 44 s47> e 7]## #33ns. #443, #3-4 33- 33# #44. - #4 3#3 434 4#7}* &3 n# 4#44#ns #3-4 n, 334# 3343 4444 4*34^4 433 34444 4# 7fst 333ns 3443 #3-4. &4 3334# 44 #3344 444 3S S# ^ 3#4 7]#3 27] 7]#44# 4#. -147- 4. ^S7||S| 7K W ^ a *11*11 9434(3) 39-41-8- til 3. 2001 2002 2003 2004 2005 2006 1. 3 9-9 3334 3 9 1341 7im - 333 333 ^9 3 1341 9433 44- - S.1S S4ir 33 data 4# 7fl3 134 2. Manipulator 2:9 7)# 1341 7M - 9493934 94 4149 manipulator 414 1341 3. 444 44 511 °14 139 4444 7H# - 3 KW 444 51144 1341 4444 414 - 600 um 4 444 44 1341 44 44 4. 5ii4 4 444 2:444 1341 44 4144# 7H# - 444 44 441 44 9> 2:444 4M 44 414 1341 5. el] °14 44 44 414 7l# 7H# 1341 - 4444, ^144 ^ manipulator 4 4443 1341 €4 4M 44 414 1. 49^ 4144 4444 2341 414 -43 9919 51134 44 2341 414 2. 499 £ii 44 2341 - Manipulator 444 2341 493 5.iLm 414 - 49^ S.S.E *u4-§- 2341 4444 414 3. 34 4-8-43 2341 - triga 43444 34 2341 414 44 33 4. 4# 4# 94 2341 — 148 — >4. f^ ^S7j|sj D 1 •• 44 7|# 441 7]# ?m - Manipulator 2:47]# /H# - 3 #4 ^4 4^-44 7D# - o] Z] ^4^- 4^4# 7H# - 3144 4444 ^444 4471# 7m 2) 2 445 : 4m 7] 4 ?14 system integration - 3 44 44 45# °]-§-4 manipulator 44 - 4^4-444 44 24 4# 7mv - 44 &4 444 7>#4; 44 4147-1 ## 44 7H# 3) 3 445- : 44 3144 44 44 system integration 4 4444 44 - efl °14 4 manipulator 4 #a] 414 44 7fl4 - 3 4-4 444 3144 44 44 4# ck 4!^ ^ oi| 4141 mi yE ‘01 ‘02 ‘03 ‘04 ‘05 ‘06 :3i S!S|(M¥) 3.5 4.0 4.5 5.0 5.0 4.0 26.0 0II^@) 8 9 8 9 10 7 51 149- 5. gzim §y 7|dh 14 7k 7|#?m 1) *4* ****** - *4* *4 ****** ^ &*f4 *4 5* *** *4j 4 4*7^ c *7)1* * *4^4 414** 4-**, 4 4 7} ^** *44 ** 445 *544 7]5*44 #. 2) *** manipulator * 4 4 *4 - sll44 *4 *** *444* sll44 ***** 7}^-#4 *45 & *444* #4. *** 5444, ^5* 5*44 5*4 *5* *4 manipulator * *7} **- *57} *^**54, *-§-7i]54 7fl1|!'4 *5*-, **5 54444 -§-5.4 4 ** manipulator 5 7} *£-] x| £-t*u}. *** 54444 **-§- 4 o] * * **7j # 7}5#4 4 5-7-1 * 5 *-§- manipulator * 7-11445* *7]] 4 7fl** ^-o>5, 444 44* 4# *5 4e*5 4 #54 55*4 5. 3) *44 &4*4 4444 - 444 **44 4* 54 444* capacitance #4 *44 ** 4 *4 4 *5*, capacitance *4*4* 444 noise 4 °!*ir *4 4 *4 **4 44*44 *444, *44 *57} 44 5**4 5. 4) *** 4* g 5#4 444 7}* 4* - *4 *** 4* 444 * 4* 4** *44** 4** *** **5* 4** **4 *5*, *44* 4**4* 5*4 *** *4 4*4 *44 4* *44 *44*5 *444, *44 557} 44 5-§- 150 5) 4## 44 #44 #444 - TRIGA 4-44 7]# ^## 4# ## 44 a# a#44 #. 4. 44 54 - 44 4## 4^44 444 Sandia 4## #44 #4# ##, 4 24 4/1* #44 4224422 7]## ?H#4-4 ##42S 4^## ##4# 44 4444. - #4, #4 a.44 44444 444444 4244 4* 4444 444444 444# #44# 44 3:444. - 44, 444 444 #444 4## 44#4444 44 4 #4 442 4# 7i]4#4 4#s4, ## 7]#4 #44 4 24 #4 4 44 4# 444# 7i]444 4# 24-# 41# 24. - #4 44 system# #442, TRIGA 44444 44 44 4# 4# #4# #44 ###224, #44# 4#4 44 44 system# #2## 44 #44 44 444# 444## 42## 44 4444. - 71144 44 #444 444## 4##4 47M #44 ##44, ##4##4=#2 ##27} #24, 4# 44#4 #44## 4 4#4# 4# ### # 4# —151 — 6. HE: S! Am- - a. 44* Afl3_* _g_4i 7]** 7^4^til ^%%% ?H °W^, zz. *<3 4^% <34 %4 ^44 %J±% 4** #4%4 4 711* 41% %4%% %4* 7H#%%4 ^%%ir T3. %&. - 44^ 444 7}44&, 3%% %*, 3ll 447^44 4^ 7]*, 5.5: 44 ^ 41444 4**4 4** 44 4^.44 % r|r 7l*ir 4^43., 444 A}*47l 41% %4%% %4# 4% jgk 4#%% 44. -152- ^ ^7>7l^ 7H# 1. 7|ea=|# SI @7^ 7k 7|# (1) 444 #4## 7]# #4 #4 4#4 44 TRIGA MARK H, m 4 44 #444 a#-! 4 4A (2) 47}# # asil7] ##44 #^-4 a# 4#4 #4 #4 4# ^4 47} 4 # #4 4 #4 4# #a}4 4# 44 4 a# ?H# 7]# 4# o^rf. (3) 71^711^. ^ 4# - 444 4^} ^7S/€4SI #711 (##^# 4#, 444 #4 #4 ##, ### ##4 ##, ^##4 3}# #) S>7l 4d# 44# # 7flsRr 4# 44. - # 44 ##-sM 444 41# 44-4 4#444 5|7>s>jl #-# # a #444 # a a#4 44 # £#g. ##4e 4# ##44. - ## 4 7114/^7114 4## 414 4# 4 44444 444444 #7}## ##44 #44 3|7> ##44 4444. (4) ##^7} - #711 #4# 444 47} 7l# 7}#4 71144# 4# ## 44, ## #44- 444 ##4 44 44# 4444 #4 7}444. - 4% #ifa #4444# 44(1,495 MUS$/4) ## 4^-4, 44 4#/###a-i #44 714 #44 4444. —153 — - 4-44^4#4 ## 7]e& #4# # $1# ^44#, #4]^ 4-# #4- 4# $}## ^<4] 4% #1 444 3# 4 4434# #4 44. (5) Science and Technology 7} # ^-S_Aj - 44"4 444 44 ^ 44# 444-4 4 4] spil 4## 4] 433# 4-44-44 ^}4, 4M] 4 ## 4M 14-#4 4% 4 33# 3! 3-3] 47}3# 7] #7]] #4 3#444. - #113#4 if## #4, 344 3#, 344# 2AM7]#, 44 44 44 #333# 3434 433 4#4#o] 3#3## 7]#7]]3# 447} 4# 3.4. - 4 4 #3 44444#4 44 44/4444 4# 4#-& #33 4 $14 444 #3#4 433 #4 44 &##7} 3 #44, 44#4 4 44## 4-444 $14 3##^}# 44# 4 $14 4## 7%#4 #434. (6) 4 #4 4-$144 3#3 44- - 4444 44-# 444 37}7]#4 444# #44 44 7%#4 4#4 4# 4 KINS4- 444 444- 44H34 4#44. - 444 37}, 444# 24- 3%7]#4=4 444 34 Pilot if# 3# 4 44 if# 44 44-0] #T44. - #44 44 444 #144 47}# 4# 14 4# ### 4# #4 44 °l 3 #44. (7) %JL #1 4 414 ##7} [1] European Commission, Nuclear Science and technology, Handbook on Decommissioning of Nuclear Installations, EUR 16211 ENC1995) [2] Idaho National Engineering Laboratory, Decontamination and Decommissioning Technology Logic Diagram (Volume II), EGG-WTD-11104, 1994 [3] IAEA Technical Report Series No. 395, State of the Art — 154 — Technology and Dismantling of Nuclear Facilities (1999). [4] M.G. Fouling(PNNL), M. Klein(SCK.CEN), J. K. Luey(PNNL) [5] *41(4#4443**), 4**(!434s), 31 A)) (4*44 3*#) 4. 7|# §i# (1) 34* -2.3 #7} (7}) 4344 7]# 3* 34 #34# 7]## 34** U, Co, Cs 4 Sr 4# 4A}3 4### *3 1 344# 3# 33 1 -2-3 333 sa}^* *343 *3*s 43 (4) 3# 7))# ^ #3 3447} *31 334#4 #343 -2.3 344# 4443 -2.3 3 s* #444. ^-34 34444 34 34343 *7} 3 B£ 4X33 1 #4 3443 ^*4 -2.33s# #34#, 433 3 3 4 43)71# #4 344 344 #337} jElir 7])443 simulation# # 4 #33S* 37}44. 3*434* 34 4X4 343-s# #3*3 * s, *33**, *##, #444, #444, 4444, is *3 3*3 * 3*14 131*13 31#3 43334 44. 24 #333* 3*434 4 4 #3-** #4 #3344# 4*343 3*4344 34 #337} 7} 3434 44 343 1*44. 44 #3*34 44 #337}* *4 3# DOE 443*3 PNNL, EPA, *3, 1# *3 43443* #4 44333 4433 43* 7lf 4# 34. s34 34*#3 37}* Site specific#* 4*4 43*3*3 4 344 47}43* 71)443 *u}. ^-4 #4434* 4*# 134 a} 3"*4 1433 334 3* 3*4 344 *34433 #a}3-34 3* 443 43333 44. 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Chemical Analysis Results of the Lagoon Samples Lagoon-I Lagoon-ll Analysis Items Sample Sample pH(26t) 5.32 4.83 U (y g/mL) : < 5 < 5 Ca (y g/mL) 2565 29200 Cr (u g/mL) ! < 1 < 1 Ni (u g/mL) j 19 1.7 Fe (y g/mL) < 1 < 1 Mg (y g/mL) 87 271 Al (y g/mL) < 5 < 5 Zn (y g/mL) 25 10 Pb (y g/mL) <5 < 5 Co (y g/mL) < 1 < 1 Mn (y g/mL) 2.2 1.8 V (y g/mL) < 1 < 1 Mo (y g/mL) < 5 < 5 B (y g/mL) < 5 < 5 Si (y g/mL) < 5 < 5 Sn (y g/mL) < 5 < 5 P (y g/mL) 20 12 NH/ (%) 9.26 17.32 NOg- (%) 69 50 I cr, so^-. F- (%) ! 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Oxalic Acid/Citric Acid/CITROX ggjggggggg Process 8 ’"' K Xc Phosphoric Acid" K x c Strong Mineral Acids0,1’ x : Xr K -X° Sulfamic Acid x ; K -X° Physical Methods Rotali ng Brushcs/1 loning' 1 p K p Vacuuming/Blasting Grit Blasting 1 p K P Hydrohlastiiig - flexible lance' , K P K p Washing J Rotating Cavitation Water .let1" p P p p — 184 — a: system decontamination is primarily intended for dose reduction for follow-up dismantlement b: hard (high concentration) process c: X used to denote Technique or Method not appearing on pertinent table and therefore deemed not appropriate for a given application d: dilute process e: considered specifically for removal of UQF2 and UF4 deposits in gaseous diffusion plants f: not effective as a chemical decon agent; marginal utility for rinsing of deposits g: process is typically preceded by an oxidizing treatment (e.g., alkaline permanganate) to oxidize chromites, if necessary h: both hard and dilute processes available; ELQVIX process is modification whereby ion exchange resins are electrocherrically treated rather than grouted I: more effective on fission product removal than Pu/U j: in organic contaminants column, may also include use of EDTA and/or other chemicals,such as AP(use of AP w'th nitric acid has shown very positive results) k: in uranium enrichment column, traditionally used for removal of uranium (typically includes use of other chemicals to improve effectiveness, such as alkaline salts fACG,, (NHJ2CO3, and others) I: effective for dissolution of UQ2 m CITROX is highly corrosive to 400 series stainless steels, use restricted to Inconel and 300 series stainless steels n: established process at the N-Reactor 0: sulphuric and phosphoric acid p: more effective than nitric acid on adherent contamination q: joints and elbows can be difficult to clean r: limited by accessibility to internal surface area (via manholes,etc.);tank internals only; piping is not cost effective s: ratings indicate loose material only; reflect tank internals; piping is not cost effective t: e.g., Cav'jet u: specifically designed for piping -185- Metals -decontamination of equipment/glove boxes/dismantled piping Large Small Components, Components (In Equipment, Hand Situ Techniques) fools" Chemical Extraction Caustic Treatment (Detergents) 1’ P Chelation'1 K ; : X° Chemical Foam" P Chemical Gel1 P Electropolishing* X" K In-Situ Electropolishing 1' K A Organic Acids' K REDOX Treatments' F xc Strong Mineral Acids1' K Physical Methods Turbulator1 K Ultrasonic Vibration"1 xc K Vibratory Finishing" K Thermal Methods Smelt Purification" K K 1 Vacuuming/Blasting j Centrifuge Cryogenic CO? Pellet Blasting 1’ K P Foam/Spongc Blasting' 1 K Xc Crit Blasting' P P Hydro blasting'' K lee Blasting K v° Washing j j I Steam Cleaning' K Ultra-High Pressure Water" K | x | ;i sirnill enough for tank immersion b effective for loose contamination c used to denote Techniciue or Method not: appearing on pertinent table & therefore deemed not appropriate for a given application d examples include COItPBX process & a recyclable chelating solvent (EDTA/Carbt>nate/Pen>x i de) for uranium e foam used as carrier for appropriate detergents and/or acids: useful for complex shapes and kxise contamination f sprayed-on gel used as carrier for appropriate detergents and/or acids g phosphoric acid; nitric acid and organic acids have also been investigated h electroswabbing i oxalic, citric sulfamic acids j C.R., LOMI, ABAC. APACE. AP/CITROX, etc. k o.g, HO, UNO;. IIPO,; IINOti is traditionally used to remove uranium; addition of HP greatly increases DP 1 very effective for components with loose contamination m also used in conjunction with aggressive chemicals (HNOs/HF) to improve DF n effective for removal of loose contamination —186 — o economically best to do as part of recycled product production than just for pure cleanup p centrifuge modification achieves higher pellet velocities for removal of fixed contamination; traditional C02 blasting not effective on fixed contamination q not effective for fixed contamination; requires impregnation of abrasives on which little data exists r water injection (air slurry blasting) and vacuum shrouds used to reduce airborne generation of conventional grit blasting; variety of different media is available (sand, alumina, glass beads, soda, etc.) s <10,000 psi t Steam Vacuum System (Kelly Vacu-MacTM) is excellent modification of this technique that combines the steam cleaning action with a HEPA vacuum system to minimize spread of contamination and "spray-back" u >10,000 psi 3. 4 El 7}. #4### 4 4 44 Lagoon 4 %l# #4# 4# 444 44 44## #7]# 4###4 - Mg. 4# #444 MM 444 4444 44. #44 M 4 #4# #4# ###44 #44# M444 MM MM Ji-4# #444 #444# M# 4## 44. #44# 44444 444 4#4 ##4 44#, ^s] 4 #44 7}# 4## 4444. #44# #44 4 44Mg. 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O -_ rr 44#4# #44 4444 4#44 447] .iH 4 4##7]| #4. — 187 — V] 444 44 4#4# #444 444 #44 44i:i 44 #447^ 7]# 7}## 447} # f $14] 4# 444. 4## 444 4# 4# 7] ^#4 4. * draining * vacuum filtration * centrifugation * thermal drying (spray drying, microwave drying). 444 -o_ #4^ fx]4 42} #Ei^]# 4444 44 #7](HIC#il Irl 44 47414-ul 44^# 44# 444. 4#4 4 #7]# 444 44 71- E.E] 4# 4^4 o_m 444 4## 444. 4-& 4^ 44 (bead resin)# 4 444 #7]# 444 44mm 44 444 4444 4444 $14. 444 4444 444 4 4 #4 44 4ms] 4* 44. 4 4 4^-4- 444 4444. 4. #44 3]]7]# 44 4 4#-§-7]# 44444 #4444 4444# 4444 #4#mm #44 44 47]### 4444 4#4#m 7}# y?4 ^]7]#4 #44 #4 4 44 44. ^ ?]]7]#4 7^4 444#* 4444 7}## 4 4* 4447] #4 4#£LJ>- O T=. 44 44#4& 4#44* 444#* 7]] 4 #4. ^m## 4*47]## #444 44^4^-g- #*4. #4 44#4 # 4 44& 4444 444## 44*4. 44 #444 4 4--$}mm# 24 44#4 44 4# 4#4 44 444, *4 44#4 *## 44# 44 # yi44 44# 4444 444 444. 444 CORPEX *4# #7#}4 4# #44 44. -188 FERROUS ALLOYS MIXED STEEL, ZINC, MAGNESIUM & TIN Place decontaminated item in designated Figure 3 : Mixed Steel Treatment Figure 4 : Ferrous Alloy Treatment Procedure Procedure MELE Associates, Inc. Technical Report -189- ^ ^ 4 9# 7] 4:9.311 #9 4 #449.314 #9 S. *931 a] 49 INIS 9#l2= KAERVCR-111/2001 #11 / 9#l #14 • 441 7]#4=A 4 7]**i s%7\ 49 49444- 4 9AM 9 4 4/31 #9* 41 #14 4* 711* 94 499, #14, 419, 949, ##N-/Ji#-AM #4444*711# 4 9 4- 4 9 4 # #4#, #19, 419/TRIGA 49AM# 441, 499, #44, 411/47M-47] #4## #44 4 4 #14#444 AM 494 #14 2001 #1 4 4 189 p. 4 5. SIKO), Sll( ) 3. 7] 210 x 297 cm %3LA>#- 4449 97H(0), 444( ), _ 44# 9.31 A]** 7] *4 #91931 a] 49444# 444-44 *#7>4 #14 #3: 4* (15-201414) 9 499 KISTEP4 - 441 494#1 7M# 4# 41 #aq49(1999. 9~ 2000. 3)a) 9*99 94144 94 4* 9 -8 .# 4*916- #7]-#3i 94 ] 47M 7]#4 7fl#4#6- #7>#1 #7Ml#-4499 9 1# ^xMl# 4]"3 -441 49##1* ;W 494 n H 1 Si4. 9 494911 4^-4141 719 4#*^. ^ 7l^#3|7>, 94 4-8.4* #7]# #7}^ 7] *7]]# ##--§• #7}# 4#. 44.44 41^-44 7]* a]#*^ ^ 4*91#7M4l 414 • 441 499 49 9, 44-4 #99 ^ 149147H#A]#& 444 99 2001494 20104-6- 9499 44 9-S--B 9 a>s>494 #AM##4 4419 20304444 4** A* 4a}#4#. 44 414 - 441 447]* 5g7 H49 94 414 - 441 441 4*946- 9##3i 41 947191-6 #4144 7]*#%* 144 9 44 4*.8-44-4 ###6: #7>#1 44 9.8-7]** s.*444 44 9-8.7]* * 141, 4#1##1, 7l*7fll #49 14 £9 4*# 47}, 44 9-8- 1 44441 94 #9 #41 #7>4 4# 4 * 1# # 4494 #9 44 911 441- 1# #71-44 7H1444 #1 14 7]** 9*444. 94 TRIGA 499 444 94w##4! 44AM4 44 44* 14 AM 111, 4* 4* 14 14 497114- 94419 914^4. 9 All# 44 = (104444) 44, 44, I#-**, 7] 91 44-, #41 44-, 911 44- TRIGA 499, #aM*44, 149944*, BIBLIOGRAPHIC INFORMATION SHEET Performing Org. Sponsoring Org. Standard Report No. INIS Subject Code Report No. Report No. KAERI/CR-111/2001 Title / Subtitle Study on the Evaluation of Decontamination & Decommissioning Technologies and Their Demands in Korea Project Manager Won Zin OH/ Dry Decontamination Technology Development and Department for Highly Radioactive Contaminant Application Researcher and K W. LEE, C. H JUNG, W. K CHOI, H J. Won, G. N. Kim, Department K J. JUNG, U. S. CHUNG, D. G. LEE, C. J. KIM, S. H KM, J. M CHUNG, S. 0. KWON Publication Korea Atomic Energy Publication Taejon Publisher March 2001 Place Research Institute Date Page 188 p. 111. & Tab. Yes(Q), No ( ) Size 210X297 cm Note Open(Q), Restricted( ), Classified Report Type Research Report Class Document Sponsoring Korea Institute of Science and Contract No. Organization Technology Evaluation & Planning Abstract (15-20 Lines) D&D market den land, the current status of the technology, technology items applicable to the do mestic market and the future prospect of technologies not self-developed in Kore a were evaluated. In the evaluation of D&D market demand and the current status of the technology, 1) the market demand was investigated on the D&D objects such as the research reactors, the nuclear power plants and the nuclear fuel cycle development facilities from 2001 to 2010, and 2) the technology demand for decommissioning of th e nuclear power plants from 2001 to 2030 were investigated. In the evaluation of the b schnology items applicable to the domestic market, 1) the analysis of the technologies der ived from the technology requirements on D&D objects and their related similar technoli Dgies was performed, and 2) the technology items applicable to the domestic market w ere derived from the evaluation of the suitability on the domestic technology requirements. The promising tec" urologies applicable to the domestic market were derived from the integrated evaluation c )f the technological factors (innovation, internationally competitive power and the difficul ty of the technology development), economical factors (domestic demand and substitute m effect of foreign currency) and domestically applicable factors (applicability on the iiidustry and a ripple effect). The background of the technology development such as business applicability and the technology demonstration effect through the integrated management of the decommissioning of TRIGA reactor and the uranium conversion facility was also analyzed. Subject Keywords Decontamination, Decommissioning, Market Demand, Technological (About 10 words) Factor, Economical Factor, Applicable Factor, Nuclear Power Plant, TRIGA Research Reactor, Nuclear Fuel Cycle Facility