IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 9.01900E+3 1.88350E+1 0 0 1 0 920 1451 1 0.0 0.0 0 0 0 0 920 1451 2 0.0 0.0 0 0 89 5 920 1451 3 9-F - 19 3AUSIRK EVAL- 79 S.TAGESEN,H.VONACH,B.STROHMAIER 920 1451 4 FIN.REP.ON RC,80 DIST-MAY80 810522 920 1451 5 IDENTIFIER=INDL/V 920 REV0 920 1451 6 FORMAT= ENDF/B-5 920 1451 7 ========================= For MT = 16 ========================= 920 1451 8 920 1451 9 9-F - 19 3AUSIRK EVAL- 79 S.TAGESEN,H.VONACH,B.STROHMAIER 920 1451 10 FIN.REP.ON RC,80 DIST-MAY80 810522 920 1451 11 HISTORY= 80 RECEIVED AT IAEA 920 1451 12 8106 DATA WERE CONVERTED IN ENDF/B FORMAT BY VP,NDS 920 1451 13 TEXT= 920 1451 14 TITLE EVALUATION OF THE CROSS-SECTIONS FOR THE REACTION 920 1451 15 F-19(N,2N)F-18 920 1451 16 AUTHOR (S.TAGESEN, H.VONACH, B.STROHMAIER) 920 1451 17 INSTITUTE (2AUSIRK) 920 1451 18 REFERENCE FINAL REPORT ON RESEARCH CONTRACT 2047/R1/RB 920 1451 19 METHOD EVALUATION 920 1451 20 ANALYSIS EVALUATION PRIMARILY BASED ON EXPERIMENTALLY MEASURED 920 1451 21 CROSS SECTIONS. ALL DATA SETS WERE CRITICALLY REVIEWED 920 1451 22 AND OBVIOUSLY ERRONEOUS DATA SETS WERE DISREGARDED. 920 1451 23 IF NECESSARY, THE DATA WERE RENORMALIZED TO RECENT 920 1451 24 VALUES OF STANDARD CROSS SECTIONS AND DECAY SCHEMES. 920 1451 25 (THE EXPERIMENTAL REFERENCES CONSIDERED ARE GIVEN 920 1451 26 UNDER 'REL-REF' FOR THE INDIVIDUAL REACTIONS.) 920 1451 27 THE CROSS SECTIONS WERE EVALUATED FOR ENERGY GROUPS 920 1451 28 BETWEEN 0.1 MEV AND 1 MEV WIDE, THE WIDTH DEPENDING 920 1451 29 ON BOTH THE SLOPE OF THE EXCITATION FUNCTIONS AND 920 1451 30 THE DENSITY OF THE AVAILABLE EXPERIMENTAL DATA. 920 1451 31 **************** PROGRAM GROUPIE (VERSION 82-2) ***************** 920 1451 32 UNSHIELDED GROUP AVERAGES USING 640 GROUPS 920 1451 33 ================================================================= 920 1451 34 920 1451 35 ==================== For MT = 103 and 107 ==================== 920 1451 36 9.01900+ 3 1.83520+ 1 0 0 1 1 920 1451 37 0.0 + 0 0.0 + 0 0 0 0 0 920 1451 38 0.0 + 0 0.0 + 0 0 0 34 3 920 1451 39 9-F - 19 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL. 920 1451 40 YK-3,(42),60 ,8109 DIST-JAN81 820212 920 1451 41 IDENTIFIER=INDL 0930 REV1 920 1451 42 FORMAT= ENDF/B-5 920 1451 43 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 920 1451 44 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 920 1451 45 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 920 1451 46 TEXT= 920 1451 47 9-F-19(N,2N)9-F-18 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 920 1451 48 9-F-19(N,P)8-0-19 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 920 1451 49 9-F-19(N,A)7-N-16 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 920 1451 50 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 920 1451 51 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 920 1451 52 OBNINSK,USSR). 920 1451 53 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 920 1451 54 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 920 1451 55 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 920 1451 56 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 920 1451 57 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 920 1451 58 KONSTANTY,32(1),PAGE 105,1979 920 1451 59 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 920 1451 60 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 920 1451 61 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 920 1451 62 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 920 1451 63 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 920 1451 64 YAD. KOSTANTY 3,(42),P.60,(1981) 920 1451 65 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP. 920 1451 66 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 920 1451 67 REACTION | V.2,P.271,IAEA,VIENNA) 920 1451 68 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 920 1451 69 -------------|-------------|---------------|------------------ 920 1451 70 9-F-19(N,2N) | 7.70E-03 | 6.30E-03 | 1.1E-02 920 1451 71 9-F-19(N,P) | 1.18 | 1.12 | 1.15 920 1451 72 9-F-19(N,A) | 14.3 | 13.8 | 13.4 920 1451 73 ================================================================= 920 1451 74 ***************** Program LINEAR (VERSION 2002-1) *************** 920 1451 75 For All Data Greater than 1.0000E-10 barns in Absolute Value 920 1451 76 Data Linearized to Within an Accuracy of .100000000 per-cent 920 1451 77 ***************** Program FIXUP (Version 2002-1) **************** 920 1451 78 Corrected ZA/AWR in All Sections-----------------------------Yes 920 1451 79 Corrected Thresholds-----------------------------------------Yes 920 1451 80 Extended Cross Sections to 20 MeV----------------------------No 920 1451 81 Allow Cross Section Deletion---------------------------------No 920 1451 82 Allow Cross Section Reconstruction---------------------------No 920 1451 83 Make All Cross Sections Non-Negative-------------------------Yes 920 1451 84 Delete Energies Not in Ascending Order-----------------------Yes 920 1451 85 Deleted Duplicate Points-------------------------------------Yes 920 1451 86 Check for Ascending MAT/MF/MT Order--------------------------Yes 920 1451 87 Check for Legal MF/MT Numbers--------------------------------Yes 920 1451 88 Allow Creation of Missing Sections---------------------------No 920 1451 89 Allow Insertion of Energy Points-----------------------------No 920 1451 90 Create Uniform Energy Grid-----------------------------------No 920 1451 91 Delete Section if Cross Section =0 at All Energies-----------Yes 920 1451 92 1 451 97 0 920 1451 93 3 16 44 0 920 1451 94 3 103 23 1 920 1451 95 3 107 29 1 920 1451 96 33 16 46 0 920 1451 97 920 1 0 98 920 0 0 99 9.01900E+3 1.88350E+1 0 0 0 0 920 3 16 100 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