


PROGRAM FIZCON VERSION 8.10                              Run on 25-Oct-2011

Input File Specification------------------------JEFF312N1731_0.stan805
Check the Entire File
Sum Up Tests will be Performed
  Fractional Difference Allowed is  0.00500
Deviant Point Check will be Omitted
Consecutive Equal Value Check will be Omitted

TAPE BEING PROCESSED IS NUMBERED    1
   LABEL IS  JEFF-3.1.2 general purpose neutron file update released Oct.2011  


 Check material  17-Cl- 37  MAT 1731


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=  4
     THE MINIMUM INCIDENT ENERGY OF  1.77369E+06(EV)
         SHOULD BE  1.00000E-05(EV) FOR Q=  0.00000E+00(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=104
     THE MINIMUM INCIDENT ENERGY OF  6.50000E+06(EV)
         SHOULD BE  6.33011E+06(EV) FOR Q= -6.16197E+06(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=105
     THE MINIMUM INCIDENT ENERGY OF  1.05000E+07(EV)
         SHOULD BE  1.00606E+07(EV) FOR Q= -9.79340E+06(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=107
     THE MINIMUM INCIDENT ENERGY OF  3.50000E+06(EV)
         SHOULD BE  1.60011E+06(EV) FOR Q= -1.55761E+06(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=650
     THE MINIMUM INCIDENT ENERGY OF  6.50000E+06(EV)
         SHOULD BE  6.33011E+06(EV) FOR Q= -6.16197E+06(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=651
     THE MINIMUM INCIDENT ENERGY OF  9.76741E+06(EV)
         SHOULD BE  9.71091E+06(EV) FOR Q= -9.45297E+06(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=652
     THE MINIMUM INCIDENT ENERGY OF  1.00000E+07(EV)
         SHOULD BE  9.76741E+06(EV) FOR Q= -9.50797E+06(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=653
     THE MINIMUM INCIDENT ENERGY OF  1.09765E+07(EV)
         SHOULD BE  1.06370E+07(EV) FOR Q= -1.03545E+07(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=654
     THE MINIMUM INCIDENT ENERGY OF  1.10000E+07(EV)
         SHOULD BE  1.09765E+07(EV) FOR Q= -1.06850E+07(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=655
     THE MINIMUM INCIDENT ENERGY OF  1.15000E+07(EV)
         SHOULD BE  1.10301E+07(EV) FOR Q= -1.07372E+07(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=657
     THE MINIMUM INCIDENT ENERGY OF  1.19895E+07(EV)
         SHOULD BE  1.18686E+07(EV) FOR Q= -1.15534E+07(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=660
     THE MINIMUM INCIDENT ENERGY OF  1.27252E+07(EV)
         SHOULD BE  1.26858E+07(EV) FOR Q= -1.23489E+07(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=661
     THE MINIMUM INCIDENT ENERGY OF  1.30000E+07(EV)
         SHOULD BE  1.27252E+07(EV) FOR Q= -1.23872E+07(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=700
     THE MINIMUM INCIDENT ENERGY OF  1.05000E+07(EV)
         SHOULD BE  1.00606E+07(EV) FOR Q= -9.79340E+06(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=701
     THE MINIMUM INCIDENT ENERGY OF  1.20000E+07(EV)
         SHOULD BE  1.16758E+07(EV) FOR Q= -1.13657E+07(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=702
     THE MINIMUM INCIDENT ENERGY OF  1.24722E+07(EV)
         SHOULD BE  1.21062E+07(EV) FOR Q= -1.17846E+07(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=703
     THE MINIMUM INCIDENT ENERGY OF  1.25000E+07(EV)
         SHOULD BE  1.24722E+07(EV) FOR Q= -1.21409E+07(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=704
     THE MINIMUM INCIDENT ENERGY OF  1.30000E+07(EV)
         SHOULD BE  1.28523E+07(EV) FOR Q= -1.25109E+07(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=705
     THE MINIMUM INCIDENT ENERGY OF  1.35000E+07(EV)
         SHOULD BE  1.30800E+07(EV) FOR Q= -1.27326E+07(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=707
     THE MINIMUM INCIDENT ENERGY OF  1.37558E+07(EV)
         SHOULD BE  1.37186E+07(EV) FOR Q= -1.33542E+07(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=708
     THE MINIMUM INCIDENT ENERGY OF  1.38359E+07(EV)
         SHOULD BE  1.37558E+07(EV) FOR Q= -1.33904E+07(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=711
     THE MINIMUM INCIDENT ENERGY OF  1.40000E+07(EV)
         SHOULD BE  1.39829E+07(EV) FOR Q= -1.36115E+07(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=712
     THE MINIMUM INCIDENT ENERGY OF  1.40742E+07(EV)
         SHOULD BE  1.40527E+07(EV) FOR Q= -1.36794E+07(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=715
     THE MINIMUM INCIDENT ENERGY OF  1.45000E+07(EV)
         SHOULD BE  1.41985E+07(EV) FOR Q= -1.38214E+07(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=800
     THE MINIMUM INCIDENT ENERGY OF  3.50000E+06(EV)
         SHOULD BE  1.60011E+06(EV) FOR Q= -1.55761E+06(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=801
     THE MINIMUM INCIDENT ENERGY OF  4.00000E+06(EV)
         SHOULD BE  2.04089E+06(EV) FOR Q= -1.98668E+06(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=802
     THE MINIMUM INCIDENT ENERGY OF  5.00000E+06(EV)
         SHOULD BE  3.25158E+06(EV) FOR Q= -3.16521E+06(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=803
     THE MINIMUM INCIDENT ENERGY OF  3.97212E+06(EV)
         SHOULD BE  3.88582E+06(EV) FOR Q= -3.78261E+06(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=804
     THE MINIMUM INCIDENT ENERGY OF  5.50000E+06(EV)
         SHOULD BE  3.97212E+06(EV) FOR Q= -3.86661E+06(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 3, MT=805
     THE MINIMUM INCIDENT ENERGY OF  7.00000E+06(EV)
         SHOULD BE  5.03638E+06(EV) FOR Q= -4.90261E+06(EV)


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=649
     NO distribution given for total (n,p) cross section distribution
         with   3 subsections given for MT 649


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=650
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 650


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=651
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 651


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=652
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 652


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=653
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 653


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=654
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 654


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=655
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 655


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=657
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 657


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=658
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 658


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=660
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 660


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=661
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 661


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=700
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 700


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=701
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 701


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=702
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 702


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=703
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 703


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=704
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 704


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=705
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 705


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=707
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 707


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=708
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 708


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=711
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 711


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=712
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 712


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=715
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 715


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=800
     NO distribution given for total (n,alpha) cross section distribution
         with   2 subsections given for MT 800
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 800


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=801
     NO distribution given for total (n,alpha) cross section distribution
         with   3 subsections given for MT 801
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 801


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=802
     NO distribution given for total (n,alpha) cross section distribution
         with   3 subsections given for MT 802
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 802


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=803
     NO distribution given for total (n,alpha) cross section distribution
         with   3 subsections given for MT 803
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 803


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=804
     NO distribution given for total (n,alpha) cross section distribution
         with   3 subsections given for MT 804
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 804


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=805
     NO distribution given for total (n,alpha) cross section distribution
         with   3 subsections given for MT 805
     SECTION DOES NOT SPAN THE SAME ENERGY RANGE AS FILE   3, MT= 805


  ERROR(S) FOUND IN MAT=1731, MF= 6, MT=849
     NO distribution given for total (n,alpha) cross section distribution
         with   3 subsections given for MT 849

     Encountered    65 errors,       0 warnings
 Done FIZCON
