ID#: D00075I303300 RSIC#: DLC-75A CODE PKG NAME: BUGLE-80 COUPLED 47-NEUTRON, 20 GAMMA-RAY GROUP, P3, CROSS SECTIONS FOR ANS 6.1.2 STUDIES COMPUTER: IBM 360/91 PACKAGED: 7/80 MOST RECENT UPDATE: DOWNLOADED: 5/09/96 ****************************************************************************** 1 tape cartridge (tar) dlc075a.tar.Z (2,727,917 bytes) ****************************************************************************** File Description Logical DCB Parameters Mode Records RECFM BLKSIZE LRECL ****************************************************************************** 1 47 Neutron, 20 Gamma-Ray Group, 16642 FB 3200 80 P3 Cross Sections (Microscopic and Macroscopic Cross Sections used in the Concrete and LWR Calculations) ID Material ID Material 1-4 H-1 49-52 Mo 5-8 B-10 53-56 Na 9-12 0-16 57-60 Mg 13-16 Cr 61-64 Al-27 17-20 Mn-55 65-68 S-32 21-24 Fe 69-72 K 25-28 Ni 73-76 Ca 29-32 Zr 77-80 LWR Core 33-36 U-235 81-84 LWR Coolant 37-40 U-238 85-88 LWR Low Carbon Steel 41-44 C-12 89-92 LWR Stainless Steel 45-48 Si 93-96 Concrete 2 47 Neutron, 20 Gamma-Ray Group, P3, Cross Sections (24 Materials) 14676 FB 3200 80 ID Material ID Material 101-l04 Li-6 149-152 Sn 105-108 Li-7 153-156 Ba 109-112 Be-9 157-160 Eu-151 113-116 N-14 161-164 Eu-153 117-120 F 165-168 Ta-181 121-124 P-31 169-172 W-182 125-128 Cl 173-176 W-183 129-132 Ti 177-180 W-184 133-136 V 181-184 W-186 137-140 Co-59 185-188 Pb 141-144 Cu 189-192 Pu-239 145-148 Nb-93 193-196 Pu-240 3 47 Neutron Group, P3 Cross Sections (23 Materials) (Neutron Only) 7437 FB 3200 80 ID Material ID Material 201-204 U-234 249-252 He-3 205-208 U-236 253-256 He-4 209-212 Pu-242 257-260 Zirc-2 213-216 Pa-233 261-264 Ag-107 217-220 Sm-149 265-268 Ag-109 ****************************************************************************** File Description Logical DCB Parameters Mode Records RECFM BLKSIZE LRECL ****************************************************************************** ID MATERIAL ID MATERIAL FB 3200 80 221-224 Gd 269-272 Cd 225-228 Am-243 273-276 Th-232 229-232 Cm-244 277-280 U-233 233-236 Am-241 281-284 Np-237 237-240 Pu-238 285-288 H-2 241-244 Pu-241 289-292 B-11 245-248 H-3 4 IBM Job Control Cards for BCD - Binary Conversion Program 3 FB 3200 80 5 Source Deck for BCD Binary Conversion Program 144 | | | 6 IBM DD Cards for BCD Binary Conversion Program 7 | | | 7 Input Data for BCD - Binary Conversion Program 1 | | | 8 IBM Job Control Cards for Concrete Source Generation Program 6 | | | 9 Source Deck for Concrete Source Generation Program 135 | | | 10 IBM DD Cards for Concrete Source Generation Program 2 | | | 11 Input Data for Concrete Source Generation Program 12 | | | 12 IBM Job Control Cards for LWR Source Generation Program 6 | | | 13 Source Deck for LWR Source Generation Program 405 | | | 14 IBM DD Cards for LWR Source Generation Program 2 | | | 15 Input Data for LWR Source Generation Program 18 | | | 16 171 Neutron, 36 Gamma-Ray Group, P3 Macroscopic Cross Sections for Concrete and LWR Problems 47056 | | | ID Material ID Material 301-304 LWR Core 313-316 LWR Stainless Steel 305-308 LWR Coolant 317-320 Concrete 309-312 LWR Low Carbon Steel ****************************************************************************** File Description Logical DCB Parameters Mode Records RECFM BLKSIZE LRECL ****************************************************************************** 17 ANISN Input for the (47n,20g) Concrete Problem 71 FB 3200 80 18 ANISN Input for the (171n,36g) Concrete Problem 106 | | | 19 ANISN Input for the (47n,20g) LWR Problem 218 | | | 20 ANISN Input for the (171n,36g) LWR Problem 649 | | | 21 Input for AMPX Modules AJAX, BONAMI, CHOX, and MALOCS (Self-Shield Concrete Materials, Collapse to 47n,20g Groups) 113 | | | 22 Input for AMPX Module NITAWL and AXMIX (Produce ANISN Microscopic and Macroscopic Cross Sections) 94 | | | 23 (47n,20g) Scalar Fluxes from ANISN Concrete Problem 1140 | | | 24 (171n,36g) Scalar Fluxes from ANISN Concrete Problem 3520 | | | 25 (47n,20g) Scalar Fluxes from ANISN LWR Problem 1676 | | | 26 (171n,36g) Scalar Fluxes from ANISN LWR Problem 5176 | | | 27 47 Neutron, 20 Gamma-Ray Group Kerma Factors from MACKLIB-IV (49 Materials) 8350 | | | ID Material ID Material ID Material ID Material 1269 H-1 1194 Si 1285 Ta-181 1050 Pu-238 1270 He-4 1149 Cl 1128 W-182 1264 Pu-239 1271 Li-6 1150 K 1129 W-183 1275 Pu-240 1272 Li-7 1195 Ca 1130 W-184 1266 Pu-241 1289 Be-9 1286 Ti 1131 W-186 1161 Pu-242 1273 B-10 1196 V 1288 Pb 1056 Am-241 1160 B-11 1191 Cr 1296 Th-232 1057 Am-243 1274 C 1197 Mn-55 1297 Pa-233 1275 N-14 1192 Fe 1260 U-233 1276 0-16 1199 Co-59 1043 U-234 1277 F 1190 Ni 1261 U-235 1156 Na-23 1295 Cu 1163 U-236 1280 Mg 1189 Nb 1262 U-238 1193 Al-27 1287 Mo 1263 Np-237 ****************************************************************************** File Description Logical DCB Parameters Mode Records RECFM BLKSIZE LRECL ****************************************************************************** 28 47 Neutron, 20 Gamma-Ray Group, P3 Cross Section with Delayed Gammas from Fission 2236 FB 3200 80 ID Material ID Material ID Material 1-4 U-235 5-8 U-238 9-12 Pu-239 29 Output from BCD - Binary Conversion Program 98 | 2660 133 30 Output from Concrete Source Generation Program 78 | | | 31 Output from LWR Source Generation Program 642 | | | ******** 110,719 EACH MASTER TAPE WRITTEN FOR DATA PACKAGE SHIPMENT HAS BEEN SCANNED BY THE RSIC CHECK PROGRAM. ENCLOSED IS THE OUTPUT EDIT WHICH SHOWS THAT THE ACCOMPANYING TAPE HAS BEEN CHECKED FOR TAPE ERRORS, HAS LISTED THE FIRST FEW RECORDS OF ANY BCD INFORMATION OF EACH FILE, CHECKED FOR BINARY RECORDS AND THE TOTAL NUMBER OF RECORDS FOR EACH FILE.