ENTRY            14803   20230315                             150614803000    1 
SUBENT        14803001   20230315                             150614803001    1 
BIB                 10         23                                 14803001    2 
TITLE      Thermal Neutron Cross Section for 125I                 14803001    3 
AUTHOR     (D.C.Santry,R.D.Werner)                                14803001    4 
REFERENCE  (R,INDC(SEC)-62,120(2),1977)                           14803001    5 
INSTITUTE  (1CANCRC)                                              14803001    6 
FACILITY   (REAC,1CANCRC) NRU reactor.                            14803001    7 
DETECTOR   (GE-IN,GELI)                                           14803001    8 
METHOD     (INTB) Irradiations in the NRU reactor for about 33    14803001    9 
           days gave an integrated flux of 7.3 x 10**20           14803001   10 
           neutrons/cm2 with depletion ratios of 2.2 for 125I     14803001   11 
           and 1.037 for 131I. Gamma-ray counting rates of the    14803001   12 
           iodine samples were measured before and after neutron  14803001   13 
           irradiations, using high resolution photon detectors.  14803001   14 
           The 35-keV gamma ray of 125I was measured with an      14803001   15 
           intrinsic Ge X-ray detector, while the 364-keV gamma   14803001   16 
           ray of 131I and 1.33-MeV gamma ray of 60Co were        14803001   17 
           measured with a Ge(Li) detector.                       14803001   18 
ANALYSIS   Calculated cross sections based on these depletion     14803001   19 
           ratios are 1030 +- 300 barns for 125I and 85 +- 50     14803001   20 
           barns for 131I.                                        14803001   21 
ERR-ANALYS (DATA-ERR) An observed scatter in results of 15 to     14803001   22 
           25% was traced to instabilities in the data            14803001   23 
           acquisition system.                                    14803001   24 
HISTORY    (20230315C) BP                                         14803001   25 
ENDBIB              23          0                                 14803001   26 
COMMON               1          3                                 14803001   27 
EN-DUMMY                                                          14803001   28 
EV                                                                14803001   29 
     0.0253                                                       14803001   30 
ENDCOMMON            3          0                                 14803001   31 
ENDSUBENT           30          0                                 1480300199999 
SUBENT        14803002   20230315                             150614803002    1 
BIB                  2          3                                 14803002    2 
REACTION   (53-I-125(N,G)53-I-126,,SIG,,MXW)                      14803002    3 
STATUS     (TABLE,,D.C.Santry+,R,INDC(SEC)-62,120(2),1977)        14803002    4 
            page 121 of R,INDC(SEC)-62,120(2),1977.               14803002    5 
ENDBIB               3          0                                 14803002    6 
NOCOMMON             0          0                                 14803002    7 
DATA                 2          1                                 14803002    8 
DATA       DATA-ERR                                               14803002    9 
B          B                                                      14803002   10 
     1030.0      300.0                                            14803002   11 
ENDDATA              3          0                                 14803002   12 
ENDSUBENT           11          0                                 1480300299999 
SUBENT        14803003   20230315                             150614803003    1 
BIB                  2          3                                 14803003    2 
REACTION   (53-I-131(N,G)53-I-132,,SIG,,MXW)                      14803003    3 
STATUS     (TABLE,,D.C.Santry+,R,INDC(SEC)-62,120(2),1977)        14803003    4 
            page 121 of R,INDC(SEC)-62,120(2),1977.               14803003    5 
ENDBIB               3          0                                 14803003    6 
NOCOMMON             0          0                                 14803003    7 
DATA                 2          1                                 14803003    8 
DATA       DATA-ERR                                               14803003    9 
B          B                                                      14803003   10 
       85.0       50.0                                            14803003   11 
ENDDATA              3          0                                 14803003   12 
ENDSUBENT           11          0                                 1480300399999 
ENDENTRY             3          0                                 1480399999999