Regional Basic Professional Training Course in Korea

More documents

Recommendations

Info

❙ 509 ❙ 8-B. Deterministic Accident Analysis (LOCA) 8-B. Deterministic Accident Analysis (LOCA) 8.7 LARGE BREAK LOSS‐OF‐COOLANT ACCIDENT (LBLOCA) 8.7.1. Background Emergency Core Cooling Systems (ECCS) are required on light water reactors to provide cooling of the reactor core in the event of a break in the reactor piping or the inadvertent opening of a relief valve or isolation valve, which are called loss‐of‐coolant accidents (LOCA). LOCA is a mode of failure for a nuclear reactor; if not managed effectively, the results of a LOCA could result in reactor core damage. Those postulated accidents result in a loss of reactor coolant at a rate in excess of the capability of the reactor makeup system from breaks in the reactor coolant pressure boundary, up to and including a break equivalent in size to the double‐ended rupture of the largest pipe of the reactor coolant system. Nuclear reactors generate heat internally; to remove this heat and convert it into useful electrical power, a coolant system is used. If this coolant flow is reduced, or lost altogether,
Page 5 and 6:
1. Nuclear Reactor Principles · 1
Page 7:
1. Nuclear Reactor Principles Regio
Page 10 and 11:
Table 1.2. Average cross sections f
Page 13 and 14:
1. Nuclear Reactor Principles ❙ 7
Page 15 and 16:
energy of the fuel nuclei. ❙ 9
Page 17 and 18:
❙ 11 ❙ 1. Nuclear Reactor Princ
Page 19 and 20:
Page 21 and 22:
Page 23 and 24:
1 Bq = 2.7x10 -5 µCi = 2.7x10 -8 m
Page 25 and 26:
1.1.5. Natural radioactive series
Page 27 and 28:
238 U 92+ 1 n0 -----> 135 Te 52 + 9
Page 29 and 30:
Page 31 and 32:
σ t = σ s + σ a = σ elastic +
Page 33 and 34:
FIG. 1.10. And here in the 1keV to
Page 35 and 36:
Page 37 and 38:
Page 39 and 40:
1.2.3.2. Neutron emission in fissio
Page 41 and 42:
Page 43 and 44:
Three possible states could then be
Page 45 and 46:
TABLE 1.3. Slowing down efficiency
Page 47 and 48:
1 UNGG/AGR CANDU PWR/BWR TABLE 1.5.
Page 49 and 50:
Page 51 and 52:
Page 53 and 54:
Page 55 and 56:
Page 57 and 58:
Page 59:
✼✼✼ REFERENCES ✼✼✼ ❙
Page 63 and 64:
2.1. Introduction C O N T E N T S 2
Page 65 and 66:
2. Radiation Protection 2.1. Introd
Page 67 and 68:
2.2.1. Exposure ❙ 61 ❙ 2. Radia
Page 69 and 70:
❙ 63 ❙ 2. Radiation Protection
Page 71 and 72:
Page 73 and 74:
2.2.4. Effective dose ❙ 67 ❙ 2.
Page 75 and 76:
Page 77 and 78:
Page 79 and 80:
Page 81 and 82:
Page 83 and 84:
schematically in Fig. (2.7). ❙ 77
Page 85 and 86:
Page 87 and 88:
The great utility of the G‐M tube
Page 89 and 90:
Page 91 and 92:
Page 93 and 94:
Page 95 and 96:
Page 97 and 98:
Page 99 and 100:
protection conditions. These factor
Page 101 and 102:
2.6.2. Effects of dose, dose‐rate
Page 103 and 104:
Page 105 and 106:
2.7. Principles of Radiological Pro
Page 107 and 108:
Page 109 and 110:
Page 111 and 112:
Page 113 and 114:
Page 115 and 116:
Page 117 and 118:
Page 119 and 120:
Page 121 and 122:
❙ 115 ❙ N 0 = N 2 1 t / t 1/ 2
Page 123 and 124:
ln 10 = μ t1/10 ≈ 3 · ln 2 = 3
Page 125:
Page 129 and 130:
C O N T E N T S | Table of Contents
Page 131:
Fig. 1 Committees for IAEA Safety S
Page 134 and 135:
Regional Basic Professional Trainin
Page 136 and 137:
Page 138 and 139:
Page 140 and 141:
Page 142 and 143:
Page 144 and 145:
Page 146 and 147:
Page 148 and 149:
Page 150 and 151:
Page 152 and 153:
Page 154 and 155:
Page 156 and 157:
Page 158 and 159:
Page 160 and 161:
Page 162 and 163:
Page 164 and 165:
Page 166 and 167:
Page 168 and 169:
Page 170 and 171:
Page 172 and 173:
Page 174 and 175:
Page 176 and 177:
Page 178 and 179:
Page 180 and 181:
Page 182 and 183:
Page 184 and 185:
Page 186 and 187:
Page 188 and 189:
Page 190 and 191:
Page 192 and 193:
Page 194 and 195:
Page 196 and 197:
Page 198 and 199:
Page 200 and 201:
Page 202 and 203:
Page 204 and 205:
Page 206 and 207:
Page 208 and 209:
Page 210 and 211:
Page 212 and 213:
Page 214 and 215:
Page 216 and 217:
Page 218 and 219:
Page 220 and 221:
Page 222 and 223:
Page 225 and 226:
Page 227 and 228:
❙ 221 ❙ 4. DESIGN OF NUCLEAR RE
Page 229 and 230:
4.1.1.2. The concept of defence in
Page 231 and 232:
4.1.2. Requirements for management
Page 233 and 234:
Page 235 and 236:
Page 237 and 238:
administrative control. ❙ 231 ❙
Page 239 and 240:
Page 241 and 242:
Page 243 and 244:
Design basis accidents ❙ 237 ❙
Page 245 and 246:
Single failure criterion ❙ 239
Page 247 and 248:
Page 249 and 250:
Page 251 and 252:
Deterministic approach The determin
Page 253 and 254:
accidents, with account taken of th
Page 255 and 256:
Fuel elements and assemblies Fig. 4
Page 257 and 258:
Reactor shutdown ❙ 251 ❙ 4. DES
Page 259 and 260:
Page 261 and 262:
Page 263 and 264:
Page 265 and 266:
functional in the event of a severe
Page 267 and 268:
4.1.5.4. Instrumentation and contro
Page 269 and 270:
Page 271 and 272:
Page 273 and 274:
Page 275 and 276:
4.1.5.9. Radiation protection Gener
Page 277 and 278:
Page 279 and 280:
Page 281 and 282:
Page 283 and 284:
Operation at a power level < 1 MW.
Page 285 and 286:
Page 287 and 288:
of these exchangers, the water is c
Page 289 and 290:
Page 291 and 292:
Page 293 and 294:
Page 295 and 296:
Page 297 and 298:
Page 299 and 300:
Fig. 4.11. HANARO Core Pool Fig. 4.
Page 301 and 302:
4.2.6.2.3 Reactor Systems ❙ 295
Page 303 and 304:
Page 305 and 306:
4.2.6.5. Neutron Activity Analysis
Page 307 and 308:
Page 309 and 310:
❏ physical separation. ❙ 303
Page 311:
5. Siting Considerations Regional B
Page 314 and 315:
5.4.2. Sources of risk 5.4.3. Evalu
Page 316 and 317:
Page 318 and 319:
Page 320 and 321:
Page 322 and 323:
Page 324 and 325:
Page 326 and 327:
Page 328 and 329:
Page 330 and 331:
Page 332 and 333:
Page 334 and 335:
Page 336 and 337:
Page 338 and 339:
Page 340 and 341:
Page 342 and 343:
Page 344 and 345:
Page 346 and 347:
Page 348 and 349:
Page 350 and 351:
Page 352 and 353:
Page 354 and 355:
Page 356 and 357:
Page 358 and 359:
Page 360 and 361:
Page 362 and 363:
Page 365 and 366:
Page 367 and 368:
6. Safety Classification Of Structu
Page 369 and 370:
Page 371 and 372:
Safety functions necessary to preve
Page 373 and 374:
Page 375 and 376:
6.1.3. Principal Safety Classes 6.
Page 377 and 378:
Page 379 and 380:
Page 381 and 382:
Page 383 and 384:
function; 6. Safety Classification
Page 385 and 386:
Page 387 and 388:
Page 389 and 390:
the safety function would be requir
Page 391 and 392:
Page 393 and 394:
Page 395 and 396:
6.3.2. Description of Quality Group
Page 397 and 398:
Page 399 and 400:
Page 401 and 402:
Page 403 and 404:
Page 405 and 406:
6.4.3. Seismic category 1: 6.4.3.1.
Page 407 and 408:
Page 409 and 410:
Page 411 and 412:
Page 413:
7. Quality Assurance Regional Basic
Page 416 and 417:
7.5.1. Manufacture Quality Assuranc
Page 418 and 419:
Page 420 and 421:
Page 422 and 423:
Page 424 and 425:
Page 426 and 427:
Page 428 and 429:
Page 430 and 431:
Page 432 and 433:
Page 434 and 435:
Page 436 and 437:
Page 438 and 439:
Page 440 and 441:
Page 442 and 443:
Page 444 and 445:
Page 446 and 447:
Page 448 and 449:
Page 450 and 451:
Page 452 and 453:
Page 454 and 455:
Page 456 and 457:
Page 458 and 459:
Page 460 and 461:
Page 462 and 463:
Page 464 and 465: Regional Basic Professional Trainin
Page 475 and 476: C O N T E N T S 8.1. INTRODUCTION |
Page 477 and 478: ❙ 471 ❙ 8-A. Deterministic Acci
Page 483 and 484: guidelines for this categorization.
Page 489 and 490: Table 8‐3 Typical Initial Conditi
Page 497 and 498: 8.5.3. Decrease in Reactor Coolant
Page 501 and 502: or by operator error, often during
Page 509: 8-B. Deterministic Accident Analysi
Page 512 and 513: | List of Tables | Table 8.7‐1 Ru
Page 563 and 564: C O N T E N T S 9.1. BASIC CONCEPT
Page 565 and 566:
9.1.1. Background 9. Probabilistic
Page 567 and 568:
❙ 561 ❙ 9. Probabilistic Safety
Page 569 and 570:
that are important for safety and d
Page 571 and 572:
Some typical uses of level 2 PSA ar
Page 573 and 574:
Release of fission products during
Page 575 and 576:
Page 577 and 578:
Page 579 and 580:
Page 581 and 582:
Page 583 and 584:
e indicated according to their spec
Page 585 and 586:
Page 587 and 588:
Page 589 and 590:
several pumps due to an inappropria
Page 591 and 592:
Page 593 and 594:
Page 595 and 596:
Parts common to a number of systems
Page 597 and 598:
Page 599 and 600:
9.4.3. Level 1 - level 2 interface
Page 601 and 602:
In-vessel processes during the late
Page 603 and 604:
Page 605 and 606:
y data, analyses and consideration
Page 607 and 608:
Page 609 and 610:
Page 611 and 612:
examples of useful insights of PSAs
Page 613 and 614:
Page 615 and 616:
Assessment -vs- demonstration. PSA
Page 617 and 618:
Page 619 and 620:
Page 621 and 622:
Page 623 and 624:
Page 625 and 626:
Page 627 and 628:
Page 629:
10-A. Limiting Conditions for Opera
Page 632 and 633:
Table 10.2 Operational Modes of Ulj
Page 634 and 635:
Page 636 and 637:
Page 638 and 639:
Page 640 and 641:
Page 642 and 643:
Page 644 and 645:
Page 646 and 647:
Page 648 and 649:
Page 650 and 651:
Page 652 and 653:
Page 654 and 655:
Page 656 and 657:
Page 658 and 659:
Page 660 and 661:
Page 662 and 663:
Page 664 and 665:
Page 666 and 667:
Page 668 and 669:
Page 670 and 671:
Page 672 and 673:
Page 675:
Page 678 and 679:
Page 680 and 681:
Page 682 and 683:
Page 684 and 685:
Page 686 and 687:
Page 688 and 689:
Page 690 and 691:
Page 692 and 693:
Page 694 and 695:
Page 696 and 697:
Page 698 and 699:
Page 700 and 701:
Page 702 and 703:
Page 705 and 706:
C O N T E N T S 11.1. THE HUMAN FAC
Page 707 and 708:
11. Human Performance: A Perspectiv
Page 709 and 710:
Page 711 and 712:
Page 713 and 714:
Methods Questions/Evaluations propo
Page 715 and 716:
documented by pencil goes through.
Page 717 and 718:
Page 719 and 720:
Page 721 and 722:
B. Model of Mistake 11. Human Perfo
Page 723 and 724:
C. Model of Slips 11. Human Perform
Page 725 and 726:
Page 727 and 728:
Page 729 and 730:
Page 731 and 732:
Page 733 and 734:
Page 735 and 736:
They can belong to one of these fam
Page 737 and 738:
Page 739 and 740:
Page 741 and 742:
Page 743 and 744:
Page 745 and 746:
Page 747:
Page 751 and 752:
Page 753 and 754:
12. Surveillance Programmes 12.1. C
Page 755 and 756:
❙ 749 ❙ 12. Surveillance Progra
Page 757 and 758:
Page 759 and 760:
12.2.2. Surveillance of integrity o
Page 761 and 762:
Containment spray systems; Chemical
Page 763 and 764:
High energy piping and associated p
Page 765 and 766:
Page 767 and 768:
Page 769 and 770:
Page 771 and 772:
Page 773 and 774:
Page 775 and 776:
failure of which might put in jeopa
Page 777 and 778:
Page 779 and 780:
12.3.6. Equipment ❙ 773 ❙ 12. S
Page 781 and 782:
The grading criteria for detection
Page 783 and 784:
Page 785 and 786:
12.4.1. General 12.4. IMPLEMENTATIO
Page 787 and 788:
monitors are part of the safety sys
Page 789 and 790:
Page 791 and 792:
Page 793 and 794:
Page 795 and 796:
inspection. ❙ 789 ❙ 12. Surveil
Page 797 and 798:
12.5.4. Example of Regulatory Inspe
Page 799:
maximum flow in addition to rated f
Page 803:
C O N T E N T S 1. The Overview of
Page 806 and 807:
Page 808 and 809:
Page 810 and 811:
Page 812 and 813:
Page 814 and 815:
Page 816 and 817:
Page 818 and 819:
Page 820 and 821:
Page 822 and 823:
Page 824 and 825:
Page 826 and 827:
Page 828 and 829:
Page 831:
15. Operational Safety Regional Bas
Page 834 and 835:
15.3. OPERATING ORGANIZATION AT KOR
Page 836 and 837:
Page 838 and 839:
Page 840 and 841:
Page 842 and 843:
Page 844 and 845:
Page 846 and 847:
Page 848 and 849:
Page 850 and 851:
Page 852 and 853:
Page 854 and 855:
Page 856 and 857:
Page 858 and 859:
Page 860 and 861:
Page 862 and 863:
Page 864 and 865:
Page 866 and 867:
Page 868 and 869:
Page 870 and 871:
Page 872 and 873:
Page 874 and 875:
Page 876 and 877:
Page 878 and 879:
Page 880 and 881:
Page 882 and 883:
Page 884 and 885:
Page 886 and 887:
Page 888 and 889:
Page 890 and 891:
Page 892 and 893:
Page 895:
16. In‐Plant Accident Management
Page 898 and 899:
16.5.3. Reference source terms Tabl
Page 900 and 901:
Page 902 and 903:
Page 904 and 905:
Page 906 and 907:
Page 908 and 909:
Page 910 and 911:
Page 912 and 913:
Page 914 and 915:
Page 916 and 917:
Page 918 and 919:
Page 920 and 921:
Page 922 and 923:
Page 924 and 925:
Page 926 and 927:
Page 928 and 929:
Page 930 and 931:
Page 932 and 933:
Page 934 and 935:
Page 936 and 937:
Page 938 and 939:
Page 940 and 941:
Page 942 and 943:
Page 944 and 945:
Page 946 and 947:
Page 948 and 949:
Page 950 and 951:
Page 952 and 953:
Page 955:
17. Radiological Emergency Planning
Page 959 and 960:
❙ 953 ❙ 17. Radiological Emerge
Page 961 and 962:
2. Emergency Classification and Res
Page 963 and 964:
Page 965 and 966:
Page 967 and 968:
Page 969 and 970:
Page 971:
Page 975 and 976:
Page 977 and 978:
19. Decommissioning 19.1. IAEA SAFE
Page 979 and 980:
❙ 973 ❙ 19. Decommissioning res
Page 981 and 982:
❙ 975 ❙ 19. Decommissioning Req
Page 983 and 984:
❙ 977 ❙ 19. Decommissioning is
Page 985 and 986:
❙ 979 ❙ 19. Decommissioning gai
Page 987 and 988:
❙ 981 ❙ 19. Decommissioning Ade
Page 989 and 990:
❙ 983 ❙ 19. Decommissioning rel
Page 991 and 992:
❙ 985 ❙ 19. Decommissioning dec
Page 993 and 994:
❙ 987 ❙ 19. Decommissioning reg
Page 995 and 996:
❙ 989 ❙ 19. Decommissioning bei
Page 997 and 998:
❙ 991 ❙ 19. Decommissioning kno
Page 999 and 1000:
❙ 993 ❙ 19. Decommissioning per
Page 1001 and 1002:
❙ 995 ❙ 19. Decommissioning par
Page 1003 and 1004:
❙ 997 ❙ 19. Decommissioning cut
Page 1005 and 1006:
from regulatory control. ❙ 999
Page 1007 and 1008:
❙ 1001 ❙ 19. Decommissioning as
Page 1009 and 1010:
material (of the order of 300 μSv
Page 1011 and 1012:
methods of decommissioning the nucl
Page 1013 and 1014:
Page 1015 and 1016:
❙ 1009 ❙ 19. Decommissioning 19
Page 1017:
20. Waste Management Regional Basic
Page 1021 and 1022:
20. Waste Management 20.1. INTRODUC
Page 1023 and 1024:
❙ 1017 ❙ 20. Waste Management h
Page 1025 and 1026:
❙ 1019 ❙ 20. Waste Management l
Page 1027 and 1028:
shall be appropriately taken into a
Page 1029 and 1030:
❙ 1023 ❙ 20. Waste Management d
Page 1031 and 1032:
❙ 1025 ❙ 20. Waste Management f
Page 1033 and 1034:
❙ 1027 ❙ 20. Waste Management T
Page 1035 and 1036:
❙ 1029 ❙ 20. Waste Management e
Page 1037 and 1038:
20.5.3. Solidification of waste The
Page 1039 and 1040:
Page 1041 and 1042:
Nuclide Half‐life Decay character
Page 1043 and 1044:
For disposal of LILW from NPPs, the
Page 1045 and 1046:
❙ 1039 ❙ 20. Waste Management c
Page 1047 and 1048:
Page 1049 and 1050:
❙ 1043 ❙ 20. Waste Management S
Page 1051 and 1052:
❙ 1045 ❙ 20. Waste Management s
Page 1053 and 1054:
❙ 1047 ❙ 20. Waste Management r
Page 1055:
❙ 1049 ❙ 20. Waste Management o
Page 1059:
C O N T E N T S 21.1. DEFINITION AN
Page 1062 and 1063:
Page 1064 and 1065:
Page 1066 and 1067:
Page 1068 and 1069:
Page 1070 and 1071:
Page 1072 and 1073:
Page 1074 and 1075:
Page 1076 and 1077:
Page 1078 and 1079:
Page 1080 and 1081:
Page 1082 and 1083:
Page 1084 and 1085:
Page 1086 and 1087:
Page 1088 and 1089:
Page 1090 and 1091:
Page 1092 and 1093:
Page 1094 and 1095:
Page 1096 and 1097:
Page 1099:
Licensing Process of Nuclear Facili
Page 1103 and 1104:
❙ 1097 ❙ Licensing Process of N
Page 1105 and 1106:
Page 1107 and 1108:
Page 1109 and 1110:
Page 1111 and 1112:
Page 1113 and 1114:
Page 1115 and 1116:
Page 1117 and 1118:
Page 1119:
Page 1123:
Page 1126 and 1127:
Page 1128 and 1129:
Page 1130 and 1131:
Page 1132 and 1133:
Page 1134 and 1135:
Page 1136 and 1137:
Page 1138 and 1139:
Page 1140 and 1141:
Page 1142 and 1143:
Page 1144 and 1145:
Page 1147 and 1148:
C O N T E N T S 1. Introduction to
Page 1149 and 1150:
Introduction Of e‐FAST and Exerci
Page 1151 and 1152:
❙ 1145 ❙ Introduction Of e‐FA
Page 1153 and 1154:
Page 1155 and 1156:
[Fig. 1.6] Schematic of RCS(Reactor
Page 1157 and 1158:
[Fig. 1.9] Schematic diagram of BOP
Page 1159 and 1160:
Page 1161 and 1162:
2.1.3. e‐FAST Function [Fig. 2.3]
Page 1163 and 1164:
2.2 USER MANUAL 2.2.1. General Guid
Page 1165 and 1166:
[Fig. 2.4] e‐FAST for KSNP 2.2.2.
Page 1167 and 1168:
14.1~2 Main Steam Line Break Inside
Page 1169 and 1170:
Summary [Fig. 2.6] Trend graph of v
Page 1171 and 1172:
Page 1173 and 1174:
[Table 3.1] Simulation result for p
Page 1175 and 1176:
Page 1177 and 1178:
Page 1179 and 1180:
[Fig. 3.1] Trend of major system pa
Page 1181 and 1182:
[Fig. 3.3]Trend of major system par
Page 1183:
Nuclear Safety Information Center (
Page 1186 and 1187:
| List of Tables | Table 1. Informa
Page 1188 and 1189:
Page 1190 and 1191:
Page 1192 and 1193:
Page 1194 and 1195:
Page 1196 and 1197:
Page 1198 and 1199:
Page 1201:
Operational Performance Information
Page 1205 and 1206:
Page 1207 and 1208:
Page 1209 and 1210:
Page 1211 and 1212:
Page 1213 and 1214:
Page 1215 and 1216:
Page 1217:
2.5. References Operational Perform
show all

Regional Basic Professional Training Course in Korea

Create successful ePaper yourself

Delete template?

Save as template?