표제지
목차
제출문 2
경·중수로 연계핵연료주기기술개발 과제 구성표 4
PART I. 연계핵연료주기 방사성폐기물 관리기술 개발(A Study on the Radioactive Waste Management for DUPIC Fuel Cycle) 6
요약문 8
SUMMARY 14
목차 26
제1장 서론 44
제2장 기체방사성폐기물 처리기술 50
제1절 방사성기체폐기물의 특성 50
1. 사용후핵연료내 핵종의 화학적 특성 50
2. 휘발성 핵분열 생성물의 특성 51
제2절 핵분열생성물의 누출특성 분석 73
1. 핵분열생성물의 원소별 휘발 거동 분석 73
2. 모의사용후 핵연료를 이용한 핵종의 휘발도 분석 76
제3절 루테늄 포집기술 개발 83
1. 서설 83
2. 루테늄의 휘발 거동 분석 85
3. 루테늄산화물의 포집 물질 선정 88
4. 루테늄 포집재 제조 120
제4절 세슘포집기술 개발 129
1. 서설 129
2. 실험 131
3. 실험결과 및 고찰 137
제3장 방사성 고체폐기물 처리 기술 180
제1절 방사성 고체폐기물의 특성분석 180
1. 방사성 고체폐기물의 특성 분석 180
2. 조사된 미산화/산화피복관의 방사능 비교분석 183
3. 방사성 고체폐기물의 발생량 추정 191
4. 고체방사성폐기물의 안정화기술 개발 192
제2절 Scrap waste 저장용기의 핵임계분석 229
1. 저장환경과 계산입력자료 229
2. 핵임계 계산 결과 230
제3절 사용후핵연료의 위험도 분석 234
제4장 M6셀용 배기체처리계통 246
제1절 M6셀용 배기체처리계통분석 246
1. 사용후핵연료 선정 및 원소별 방사능량 246
2. DUPIC 핵연료 제조조건 249
3. 제조 furnace 별 기체폐기물의 예상발생율 249
4. 제조 furnace 별 배기체처리 공정도와 각 단위공정의 설계기준 251
5. 각 제조공정별 핵종별 방사능 흐름도 및 허용기준치와의 비교 254
제2절 기체방사성폐기물 처리 설비 설계 및 제작 263
1. 설계 기준 263
2. 단위장치의 상세설계 269
3. 방사성배기체 처리 설비 제작 276
제3절 방사성배기체 제어장치 개요 및 장치 별 처리효율 286
1. 제어장치개요 286
2. 장치별 처리효율 289
3. 모의배기체 제조 및 공급 290
4. 실험방법 290
5. 실험결과 291
제5장 결론 및 건의사항 296
APPENDIX 300
Appendix 1. Input data for source term caIculation 302
Appendix 2. Activities of Nuclides in Spent Fuel 304
Appendix 3. Mass of Elements in Spent Fuel 314
Appendix 4. Report on fabrication of radioactive off-gas treatment system 318
l. 제작계획서 320
2. 승인용 제작용 상세 설계도면 & 계산근거 323
3. 제작공정표 324
4. 제작도면 325
5. 시험 & 검사성적서 333
6. 제작보고서 339
7. 부분품 Catalogue & 구입처 340
PART II. DUPIC 핵연료 제조관련 고방사성물질 화학분석기술 개발(Developement of the Analytical Techniques for Highly Radioactive Materials related to the DUPIC Fuel Manufacturing) 350
요약문 352
SUMMARY 358
목차 368
제1장 서론 384
제2장 화학분석을 위한 모의 사용후핵연료 용해 388
제1절 가압경수로 사용후핵연료의 특성 389
1. 사용후핵연료의 화학적 특성 389
2. 불용성잔유물의 화학적 특성 391
3. 사용후핵연료의 용해거동 398
4. 불용성잔유물의 용해거동 401
5. 사용후핵연료 용해장치의 구성 406
6. 사용후핵연료의 용해매질 412
참고문헌 415
제2절 모의 사용후핵연료의 용해 417
1. 실험 417
2. 실험 방법 418
3. 결과 및 고찰 424
참고문헌 433
제3절 루테늄의 용해 434
1. 실험 434
2. 실험방법 436
3. 결과 및 고찰 437
참고문헌 439
제3장 우라늄 용액의 자유산도 측정 442
제1절 자유산도 측정 및 핵분열생성물의 영향 442
1. 실험 445
2. 실험방법 447
2. 결과 및 고찰 450
참고문헌 481
제2절 알칼리적정에 의한 자유산도 측정절차서 483
1. 개요 483
2. 적용범위 483
3. 기기 및 시약 484
4. 분석과정 485
5. 계산 및 결과표시 486
6. 정확도 및 정밀도 486
7. 방해물질 487
8. 참고문헌 487
제3절 옥살산염 착화제 용액에서 자유산도 측정 절차서 488
1. 개요 488
2. 적용범위 488
3. 기기 및 시약 489
4. 분석 과정 490
5. 계산 및 결과표시 492
6. 정확도 및 정밀도 492
7. 방해물질 492
8. 참고문헌 492
제4절 옥살산염/불산염 혼합착화제 용액에서 자유산도 측정 절차서 493
1. 개요 493
2. 적용범위 493
3. 기기 및 시약 494
4. 분석과정 495
5. 계산 및 결과표시 497
6. 정확도 및 정밀도 497
7. 방해물질 497
8. 참고문헌 498
제5절 산 적가법에 의한 미량의 자유산 측정 절차서 499
1. 개요 499
2. 적용범위 499
3. 기기 및 시약 499
4. 분석 과정 501
5. 계산 및 결과표시 501
6. 정확도 및 정밀도 502
7. 방해물질 502
8. 참고문헌 502
제4장 악티늄족원소 분석 506
제1절 전위차적정법에 의한 우라늄 정량 506
1. 자동화 적정장치의 적용 506
2. 우라늄의 전위차적정에 미치는 불순물 영향 516
참고문헌 524
제2절 UV/Vis 흡수분광분석법에 의한 우라늄의 정량 525
1. 실험 526
2. 실험방법 527
3. 결과 및 고찰 532
참고문헌 560
제3절 악티늄족원소 분석을 위한 분리 561
1. 악티늄족윈소의 화학적 분리 특성 561
2. 악티늄족원소 정량을 위한 분리 570
3. 알파분광법에 의한 악티늄족원소의 정량 579
참고문헌 596
제5장 핵분열생성물 분석 602
제1절 핵분열생성물의 군분리 602
1. 실험 603
2. 실험 방법 604
3. 결과 및 고찰 605
참고문헌 613
제2절 희토류 금속혼합물중 Sm의 개별분리 및 동위원소비 측정 614
1. 실험 616
2. 실험 방법 617
3. 결과 및 고찰 617
참고문헌 627
제3절 루테늄 분리 및 분석 629
1. 실험 630
2. 결과 및 고찰 635
참고문헌 653
제4절 핵분열생성물 정량을 위한 ICP-AES의 규격 654
1. 분석시료의 특성 655
2. ICP-AES의 특성 659
3. 방사선 차폐장치(shielding system) 668
4. 핵분열생성물 모의 혼합용액 분석 675
참고문헌 710
제6장 결론 및 건의사항 716
서지정보양식(BIBLIOGRAPHIC INFORMATION SHEET) 719
PART I. 연계핵연료주기 방사성폐기물 관리기술 개발(A Study on the Radioactive Waste Management for DUPIC Fuel Cycle) 36
Table 2.1.1. Chemical state of chemical species in spent fuel and estimated... 52
Table 2.1.2. The isotopes of ruthenium 54
Table 2.1.3. The physical properties of ruthenium 55
Table 2.1.4. Observed total vapour pressures and calculated partial pressures... 60
Table 2.1.5. Physical properties of cesium 65
Table 2.1.6. The radioactive isotopes of cesium 66
Table 2.2.1. 열중량분석 조건 74
Table 2.2.2. Physical properties of cesium oxides 77
Table 2.2.3. Simfuel composition 78
Table 2.2.4. Digital TGA data of simfuel for various case 82
Table 2.2.5. Digital TGA data of simfuel at 400℃ 82
Table 2.2.6. Weight loss rate at 1400℃ 82
Table 2.3.1. Conditions of thermogravimetric analysis 86
Table 2.3.2. Expected reaction of metal ruthenates 91
Table 2.3.3. Samples chosen by trapping material of ruthenium oxides 92
Table 2.3.4. Stoichiometric capacities of trapping materials 108
Table 2.3.5. Thermal stability of trapping materials by TGA 113
Table 2.3.6. Behavior of ruthenium trapped on yttria in OREOX condition 125
Table 2.4.1. Physical and chemical properties of CsN0₃와 CsI 132
Table 2.4.2. Chemical properties of fly ash 133
Table 2.4.3. Composition of slip(I) 135
Table 2.4.4. Composition of slip(II) 136
Table 2.4.5. Composition of slip(III) 136
Table 2.4.6. Phase analysis results with changing cesium loading... 154
Table 2.4.7. Phase analysis results with changing cesium loading... 163
Table 2.4.8. Observation of filter 170
Table 2.4.9. XRF(X-ray Fluorescence) results 175
Table 3.1.1. Solid wastes arising during decladding of PWR... 182
Table 3.1.2. Specification of Zircaloy specimen for radioactivity analysis 184
Table 3.1.3. Specific radioactivities of radionuc1ides in hull 185
Table 3.1.4. Fraction of radiocativity for actinides 190
Table 3.1.5. Fraction of radioactivity for fission products 190
Table 3.1.6. Waste arisings 192
Table 3.1.7. Chemical composition of domestic fly ash 194
Table 3.1.8. Physical properties of fly ash 196
Table 3.1.9. Composition of simulated high level radwaste 196
Table 3.1.10. Composition of base glasses 197
Table 3.1.11. Waste glass composition 201
Table 3.1.12. Composition of synthetic ground water 202
Table 3.1.13. Composition of synthetic sea water 202
Table 3.1.14. Glass fomation characteristics of base glasses 203
Table 3.1.15. Glass formation characteristics of waste glasses 205
Table 3.1.16. Cumulative fraction realeased of Na, Cs, B, Si, AI and U... 206
Table 3.1.17. Leach rates of Na, Cs, B, Si, AI and U from waste... 207
Table 3.1.18. Leach rates of Na, Cs and Sr from simulated HLW... 207
Table 3.1.19. Composition of base glass for filter waste 218
Table 3.1.20. Composition of simulated spent filter waste glass 219
Table 3.1.21. Chemical composition of simulated spent filter 220
Table 3.1.22. Fraction of volatility before and after vitrification process 221
Table 3.1.23. Leach rate of simulated spent filter waste 221
Table 3.1.24. EPMA results for spent filter waste glass sample after leaching 227
Table 3.2.1. Distribution of fission products for spent fuel 230
Table 3.3.1. ORIGEN 2 lnput Data far Spent DUPIC and CANDU fuel 236
Table 3.3.4. Heavy metal data for once-through and DUPIC cycle 243
Table 4.1.1. Candidate fuels for DUPIC fuel manufacturing 247
Table 4.1.2. Offgas arisings during DUPIC fuel assembly manufacturing 248
Table 4.1.3. Operation conditions for DUPIC fuel manufacturing process 250
Table 4.1.4. Estimated processwise arising of gaseous waste... 250
Table 4.1.5. Discharge rate of radionuc1ides during low temperature oxidation 252
Table 4.1.6. Design criteria of off-gas treatment system 255
Table 4.1.7. Flow chart of off-gas treatment system... 256
Table 4.1.8. Flow chart of off-gas treatment system for low and... 257
Table 4.1.9. Flow chart of off-gas treatment system for reducing furnace 258
Table 4.1.10. Flow chart of off-gas treatment system for sintering furnace 259
Table 4.1.11. Summary of arising and activity for gaseous waste... 260
Table 4.1.12. Allowable emission level to the M6 cell ventilation... 262
Table 4.2.1. Furnaces available during DUPIC fuel manufacturing 264
Table 4.2.2. Fission product release in DUPIC process 265
Table 4.2.3. Estimated gaseous waste arisings from OREOX... 266
Table 4.2.4. Design criteria for offgas treament system 268
Table 4.2.5. Flowrate at each point in the offgas treatment system... 269
Table 4.2.6. 배기체 처리 장치 제작 개요 275
Table 4.3.1. Unitwise removal efficiency for the offgas treatment system 292
PART II. DUPIC 핵연료 제조관련 고방사성물질 화학분석기술 개발(Developement of the Analytical Techniques for Highly Radioactive Materials related to the DUPIC Fuel Manufacturing) 370
Table 2.1.1. Composition of the residues after dissolution of spent fuel... 394
Table 2.1.2. Chemical state of the fission products, actinides of the... 399
Table 2.1.3. Dissolution rate constant, k 399
Table 2.1.4. Dissolution media of irradiated fuel elements 413
Table 2.1.5. Dissolution media for nuclear fuel elements 414
Table 2.1.6. Dissolution of sheathing materials 414
Table 2.2.1. Components of the SIMFUEL 420
Table 2.2.2. Acids for the decomposition of two membrane filter papers 420
Table 2.2.3. Quantity of insoluble residues in SIMFUEL 428
Table 2.2.4. Dissolution media for some insoluble residues in metallic... 428
Table 2.2.5. Analytical results for redissolved solution of insoluble... 430
Table 2.3.1. Results of dissolution for ruthenium by acid digestion method 438
Table 2.3.2. Results of dissolution for ruthenium+uranium mixtures by... 438
Table 4.1.1. Titration results of the uranium standard solution 511
Table 4.1.2. Titration results of the uranium sample 511
Table 4.1.3. Titration results of the uranium standard solution 513
Table 4.1.4. Estimated(A) amounts of fission products in PWR spent fuel 520
Table 4.1.5. Effects of Foreign ions on the potentiometric titration for... 521
Table 4.2.1. Parameters for UV/Vis spectrophotometer 530
Table 4.2.2. Concentration of some fission products in the PWR spent fuel 530
Table 4.2.3. Linear Regression Data from Fig. 4.2.3 535
Table 4.2.4. Linear Regression Data from Fig. 4.2.4 535
Table 4.2.5. Linear Regression Data from Fig. 4.2.6 541
Table 4.2.6. Linear Regression Data in Various Concentrations of Nitric Acid 541
Table 4.2.7. Determination of Uranium in Uranyl Nitrate Solutions 543
Table 4.2.8. Spectral interferences of some fission products on... 558
Table 4.3.1. Separation of uramium and plutonium by chromatography 568
Table 4.3.2. Separation of plutonium on ion exchangers 569
Table 4.3.3. Recovery of actinide elements for different chemical process 574
Table 4.3.4. activity of gamma emitting nuclides in separated samples 574
Table 4.3.5. Gross alpha activity in separated samples 590
Table 4.3.6. Activity of alpha emitting nuclides in alpha spectrometry 590
Table 5.1.1. Extraction yields of uranium depending on the concentrations 607
Table 5.1.2. Eon yields of relevant elements depending on the acidity 607
Table 5.1.3. Extraction yields of U and Zr depending on the anion, [NO₃⁻] 609
Table 5.1.4. Extraction yields of relevant elements depending on the... 609
Table 5.2.1. Isotope percentage of Sm separated from a mixture of rare... 625
Table 5.4.1. Chemical composition and radioactivity of PWR spent fuel 657
Table 5.4.2. Estimated chemical composition of sample solution after eparation... 658
Table 5.4.3. Characteristic analytical lines of elements used in the... 663
Table 5.4.4. Comparison of the features between CID and SCD detectors 666
Table 5.4.5. Comparison between Electro-optical Characteristics of CID, CCD and PMT as detectors 667
Table 5.4.6. Sensitive analytical lines of metals in the range of ultra... 676
Table 5.4.7. Standard metal solutions used for preparation of a mixed... 677
Table 5.4.8. Chemical composition of artificial solution-1 of mixed fission products 679
Table 5.4.9. Chemical composition of artificial solution-2 of mixed fission products 680
Table 5.4.10. Analysis of an artificial solution of mixed fission products... 705
Table 5.4.11. Analysis of an artificial solution of mixed fission products... 706
Table 5.4.12. Analytical results of fission products in an artificial... 707
PART I. 연계핵연료주기 방사성폐기물 관리기술 개발(A Study on the Radioactive Waste Management for DUPIC Fuel Cycle) 28
Fig. 2.1.1. Effect of oxygen pressure on vapor pressure... 61
Fig. 2.1.2. The amount of RuO₄(g)in the vapor over RuO₂(s) 63
Fig. 2.1.3. The Cs-O binary diagram(0~80 at. % oxygen),... 69
Fig. 2.2.1. TGA curves of RuO₂ 75
Fig. 2.2.2. TGA curves of Simulated spent fuel 80
Fig. 2.2.3. TGA curves of Simfuel containing low temperature oxidation process 81
Fig. 2.3.1. TGA curve of the RuO₂ heated up to 1400℃ in air 87
Fig. 2.3.2. Volatility of the RuO₂ maintained for an hour... 89
Fig. 2.3.3. TGA curve of the RuCl₃ heated up to 1400℃... 90
Fig. 2.3.4. X-ray diffraction pattern of RuO₂ and Fe₂O₃... 94
Fig. 2.3.5. X-ray diffraction pattern of RuO₂ and TiO₂... 95
Fig. 2.3.6. X-ray photoelectron spectroscopy of RuO₂ and Fe₂O₃... 96
Fig. 2.3.7. X-ray diffraction pattern of RuO₂ and Fe₂O₃, TiO₂... 97
Fig. 2.3.8. X-ray diffraction pattern of RuO₂ and BaC0₃ mixture heated up to 1200℃ in air 99
Fig. 2.3.9. X-ray diffraction pattern of RuO₂ and CaC0₃ mixture... 100
Fig. 2.3.10. X-ray diffraction pattern of RuO₂ and Y₂O₃ mixture... 101
Fig. 2.3.11. X-ray photoelectron spectroscopy of Ru0₂ and Y₂O₃... 102
Fig. 2.3.12. X-ray diffraction pattern of Ru0₂ and Nd₂O₃ mixture... 103
Fig. 2.3.13. X-ray diffraction pattern of RuO₂ and Li₂O mixture... 105
Fig. 2.3.14. X-ray diffraction pattern of RuO₂ and Y₂O₃ mixtures reacted at... 106
Fig. 2.3.15. Scanning electron micrograph of RuO₂ and BaCO₃... 107
Fig. 2.3.16. Scanning electron micrograph of RuO₂ and Y₂O₃... 109
Fig. 2.3.17. TGA curve of trapping materials 112
Fig. 2.3.18. TGA curve of RuO₂ and Fe₂O₃ mixture heated... 114
Fig. 2.3.19. TGA curve of RuO₂ and TiO₂ mixture heated... 115
Fig. 2.3.20. TGA curve of RuO₂ and BaCO₃ mixture heated... 117
Fig. 2.3.21. TGA curve of RuO₂ and Y₂O₃ mixture heated... 119
Fig. 2.3.22. TGA curve of RuO₂ and Li₂O mixture heated... 121
Fig. 2.3.23. TG-DT Analysis on Stoichiometric Mixture of RuO₂ and Y₂O₃ in Air Atmosphere(Oxidation) 122
Fig. 2.3.24. TG-DT Analysis on Yttrium Ruthenate(Y₂Ru₂O₇)in Pure Hydrogen Atmosphere(Reduction) 123
Fig. 2.3.25. TG-DT Analysis on Reduced Yttrium Ruthenate in Air Atmosphere(Reoxidation) 124
Fig. 2.4.1. X-ray diffraction pattern of fly ash 138
Fig. 2.4.2. SEM photograph of fly ash 139
Fig. 2.4.3. DTA and TGA curve of the mixture of fly ash and CsNO₃ 141
Fig. 2.4.4. X-ray diffraction pattern for the reaction product of... 142
Fig. 2.4.5. SEM photograph for the reaction product of ... 143
Fig. 2.4.6. DTA and TGA curves of the mixture of fly ash and CsI 145
Fig. 2.4.7. X-ray diffraction pattern for the reaction product of... 146
Fig. 2.4.8. SEM photograph for the reaction product of... 148
Fig. 2.4.9. Color change as a function of cesium loading quantity... 149
Fig. 2.4.10. TGA curve for the sample of cesium loading quantity... 150
Fig. 2.4.11. TGA curve for the sample of cesium loading quantity... 151
Fig. 2.4.12. TGA curve for the sample of cesium loading quantity... 152
Fig. 2.4.13. X-ray diffraction pattern of cesium trapped fly ashes... 155
Fig. 2.4.14. The fraction of CsAlSiO₄ to pollucite... 157
Fig. 2.4.15. Effect of the cesium trapped amount... 159
Fig. 2.4.16. Relationship between the fraction of... 160
Fig. 2.4.17. Color change as a function of cesium loading quantity... 162
Fig. 2.4.18. X-ray diffraction pattern of cesium trapped fly ashes... 164
Fig. 2.4.19. The fraction of CsAlSiO₄ to pollucite... 166
Fig. 2.4.20. Effect of the cesium loading quantity on... 167
Fig. 2.4.21. Relationship between the fraction of... 169
Fig. 2.4.22. Ceramic foam filters of fly ash (A) before trapping... 172
Fig. 2.4.23. X-ray diffraction pattern of fly ash filter loaded... 173
Fig. 2.4.24. X-ray diffraction pattern of fly ash filter loaded... 174
Fig. 3.1.1. Specific α-activity in hull at its elevated burnup 187
Fig. 3.1.2. Specific γ-activity in hull at its elevated burnup 188
Fig. 3.1.3. Specific γ-activity in hull at its elevated burnup 189
Fig. 3.1.4. Soxhlet leach test apparatus 199
Fig. 3.1.5. Composition of base glasses 204
Fig. 3.1.6. Dependency of leach rate on leaching temperature 209
Fig. 3.1.7. Dependency of leach rate on leachate 209
Fig. 3.1.8. Comparison of vitrified sample(No.1) before... 211
Fig. 3.1.9. Comparison of vitrified sample(No.2) before... 212
Fig. 3.1.10. Comparison of vitrified sample(No.9) before... 213
Fig. 3.1.11. Comparison of vitrified sample(No.10) before... 214
Fig. 3.1.12. Comparison of vitrified sample(No.11) before... 215
Fig. 3.1.13. Comparison of vitrified sample(No.13) before... 216
Fig. 3.1.14. Comparison of vitrified sample(No.14) before... 217
Fig. 3.1.15. XRD result for reaction product between cesium nitrate and fly ash 222
Fig. 3.1.16. TG/DTA analysis for simulated spent filter 222
Fig. 3.1.17. XRD result for simulated spent filter waste glass(W-20) 223
Fig. 3.1.18. SEM photograph of spent filter waste glass product... 225
Fig. 3.1.19. SEM photograph of waste glass products containing... 226
Fig. 3.2.1. Cross section of monolith 231
Fig. 3.2.2. Cross section of stainless steel container 232
Fig. 3.2.3. Dependency of Keff on water density[이미지참조] 233
Fig. 3.3.1. Radioactive ingestion hazard index of spent PWR, DUPlC and CANDU fuels 235
Fig. 3.3.2. Comparison of actinides contained in spent PWR35, DUPlC16 and CANDU fuel 237
Fig. 3.3.3. Comparison of actinides contained in spent PWR50, DUPlC13 and CANDU fuel 238
Fig. 3.3.4. Comparison of radioactive ingestion hazard index of spent PWR, DUPIC and CANDU fuels 240
Fig. 3.3.5. Comparison of radioactive ingestion hazard index of once-though and DUPIC cycle 240
Fig. 3.3.6. Comparison of radioactive ingestion hazard index of once-though and DUPIC cycle per unit electric power 242
Fig. 4.1.1. Flow diagram of offgas treatment system for DUPIC fuel... 253
PART II. DUPIC 핵연료 제조관련 고방사성물질 화학분석기술 개발(Developement of the Analytical Techniques for Highly Radioactive Materials related to the DUPIC Fuel Manufacturing) 374
Fig. 2.1.1. Chemical state of the fission products in oxide fuels 390
Fig. 2.1.2. Relation between the amount of insoluble residue... 393
Fig. 2.1.3. Particle size distribution of suspended insoluble... 396
Fig. 2.1.4. Time dependence of the dissolution fractions of... 402
Fig. 2.1.5. Dissolver apparatus using ozone as oxidizing agent 404
Fig. 2.1.6. Electrolytic dissolver arrangement 405
Fig. 2.1.7. Dissolution apparatus and monitors installed in the hot... 409
Fig. 2.1.8. Dissolution and gas collection apparatus at the ANS 410
Fig. 2.1.9. Dissolution assembly for irradiated uranium samples by... 411
Fig. 2.2.1. Dissolution apparatus for simulated UO₂ fuel sample 419
Fig. 2.2.2. Experimental procedures-I for the dissolution of the insoluble residues 422
Fig. 2.2.3. Experimental procedures-II for the dissolution of the insoluble residues 423
Fig. 2.3.1. Acid digestion bomb for the dissolution of... 435
Fig. 3.1.1. Gran plot for the titration of a HNO₃ solution with... 452
Fig. 3.1.2. Dependence of Gran plot on uranium concentration... 454
Fig. 3.1.3. Gran plot for the titration of a concentrated... 456
Fig. 3.1.4. Effect of uranium concentration on the alkali-... 459
Fig. 3.1.5. Gran plot profiles with an increase in free acid at a constant concentration of uranium in 0.20 M Na₂C₂O₄:... 462
Fig. 3.1.6. Effect of uranium concentration on the alkali-... 464
Fig. 3.1.7. Gran plot for the titration of a nitric acid solution... 466
Fig. 3.1.8. Gran plot for the titration of a free acid in... 468
Fig. 3.1.9. Gran plot for the alkali-titrimetric determination... 470
Fig. 3.1.10. Gran plot for the alkali-titrimetric determination... 471
Fig. 3.1.11. Gran plot for the alkali-titrimetric determination... 472
Fig. 3.1.12. Gran plot for the alkali-titrimetric determination... 473
Fig. 3.1.13. Gran plot for the alkali-titrimetric determination... 475
Fig. 3.1.14. Gran plot for the alkali-titrimetric determination... 476
Fig. 3.1.15. Gran plot for the alkali-titrimetric determination... 477
Fig. 3.1.16. Gran plot for the alkali-titrimetric determination... 478
Fig. 3.1.17. Gran plot for the alkali-titrimetric determination... 480
Fig. 4.1.1. x-control chart of the titration results[이미지참조] 514
Fig. 4.1.2. Schematic diagram of potentiometric titration system 514
Fig. 4.2.1. Baselines of water and 4M HNO₃ 531
Fig. 4.2.2. Absorption spectra of UO₂(NO₃)₂ solution(21.70 g/L)... 533
Fig. 4.2.3. Absorbance of uranium(21.70 g/L)... 536
Fig. 4.2.4. Absorbance in various uranium concentration... 537
Fig. 4.2.5. Absorption spectra of UO₂(NO₃)₂ in 2.0 M HNO₃... 539
Fig. 4.2.6. Absorbance spectrum of uranium in 2M HNO₃ 540
Fig. 4.2.7. Absorbance spectrum of Nd in 3M HNO₃ 545
Fig. 4.2.8. Absorbance spectra of Ce(IV)in 3M HNO₃ 546
Fig. 4.2.9. Absorbance spectra of Ce(IV)(150 mg/L)... 548
Fig. 4.2.10. Absorbance spectra of RuNO3⁺ in 3M HNO₃ 549
Fig. 4.2.11. Absorbance spectra of RuNO3⁺(150 mg/L)... 550
Fig. 4.2.12. Absorbance spectra of Ru3⁺ in 3M HNO₃ 552
Fig. 4.2.13. Absorbance spectra of Pd2⁺ in 3M HNO₃ 553
Fig. 4.2.14. Absorbance spectra of Pd2⁺(150 mg/L)... 555
Fig. 4.2.15. Absorbance spectra of Rh3⁺ in 3M HNO₃ 556
Fig. 4.2.16. Absorbance spectra of Rh3⁺(150 mg/L)... 557
Fig. 4.3.1. Specially designed separatory funnel for the phase separation 572
Fig. 4.3.2. Alpha spectra of aqueous solution after first TBP extraction(S2) 575
Fig. 4.3.3. Chemical separation schematics of dissolved solution 578
Fig. 4.3.4. Configuration of glove boxes for separation and electro-deposition 582
Fig. 4.3.5. Electro-deposition cell for alpha spectroscopy 584
Fig. 4.3.6. Schematics of alpha spectroscopy system 588
Fig. 4.3.7. Gamma spectra of diluted dissolved solution(S1) 591
Fig. 4.3.8. Alpha spectra of diluted dissolved solution(S1) 592
Fig. 4.3.9. Alpha spectra of OXAL process solution after TBP extraction(S4) 593
Fig. 4.3.10. Recovery of Am-241 with various electro-deposition time 594
Fig. 5.1.1. Extraction yields of relevant elements depending on the acidity 608
Fig. 5.1.2. Extraction yields of relevant elements depending on the TBP/... 611
Fig. 5.2.1. The MAT262 Cup Configuration 618
Fig. 5.2.2. Chromatogram of rare earth ions with HPIC... 620
Fig. 5.2.3. A mass scan display for Sm peaks in Faraday... 621
Fig. 5.2.4. Elements of Natural or in Fission, from mass 140 to 154 623
Fig. 5.2.5. Internal Precision(2SE)in the measurement of 150/152,... 624
Fig. 5.2.6. External Reproducibility in the measurement of 150/152,... 626
Fig. 5.3.1. Distribution coefficients of U(VI) and Ru(III,IV)... 637
Fig. 5.3.2. Absorption spectra of some solutions of ruthenium(III, IV)in hydrochloric acid;... 639
Fig. 5.3.3. Absorption spectra of chloro or nitrosyl species of ruthenium(III, IV);... 640
Fig. 5.3.4. Effect of nitric acid on the adsorption of UO₂²⁺ in... 642
Fig. 5.3.5. Effect of hydrofluoric acid on the adsorption of UO₂²⁺... 643
Fig. 5.3.6. Effect of HCl concentration in eluent on the elution of ruthenium;... 645
Fig. 5.3.7. Effect of ageing on the elution of ruthenium in 0.10 M HCl solution;... 647
Fig. 5.3.8. Effect of ageing on the absorption spectrum of chlororuthenium(III) species... 648
Fig. 5.3.9. Effect of ageing on the absorption spectrum of chlororuthenium(III) species... 650
Fig. 5.4.1. Linear correlation between the true value and the analytical result of Ba... 687
Fig. 5.4.2. Linear correlation between the true value and the analytical result of Cd... 688
Fig. 5.4.3. Linear correlation between the true value and the analytical result of Ce... 689
Fig. 5.4.4. Linear correlation between the true value and the analytical result of Eu... 690
Fig. 5.4.5. Linear correlation between the true value and the analytical result of Gd... 691
Fig. 5.4.6. Linear correlation between the true value and the analytical result of La... 692
Fig. 5.4.7. Linear correlation between the true value and the analytical result of Mo... 693
Fig. 5.4.8. Linear correlation between the true value and the analytical result of Nd... 694
Fig. 5.4.9. Linear correlation between the true value and the analytical result of Pd... 695
Fig. 5.4.10. Linear correlation between the true value and the analyticalresult of Pr... 696
Fig. 5.4.11. Linear correlation between the true value and the analytical result of Rh... 697
Fig. 5.4.12-1. Linear correlation between the true value and the analytical result of Ru... 698
Fig. 5.4.12-2. Linear correlation between the true value and the analytical result of Ru... 699
Fig. 5.4.13. Linear correlation between the true value and the analytical result of Sm... 700
Fig. 5.4.14. Linear correlation between the true value and the analytical result of Sr... 701
Fig. 5.4.15. Linear correlation between the true value and the analytical result of Te... 702
Fig. 5.4.16. Linear correlation between the true value and the analytical result of Y... 703
Fig. 5.4.17. Linear correlation between the true value and the analytical result of Zr... 704