Average Neutron Total Cross Sections in the Unresolved by H Derrien; Oak Ridge National Laboratory. .; United States.

By H Derrien; Oak Ridge National Laboratory. .; United States. Dept. of Energy.; United States. Dept. of Energy. Office of Scientific and Technical Information

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Extra resources for Average Neutron Total Cross Sections in the Unresolved Energy Range From ORELA High Resolutio Transmission Measurements

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69260. 69760. 70260. 70760. 71260. 71760. 72260. 72760. 73260. 73760. 74260. 74760. 75260. 75760. 76260. 76760. 77260. 77760. 78260. 78760. ) E (eV) 79260. 79760. 80260. 80760. 81260. 81760. 82260. 82760. 83260. 83760. 84260. 84760. 85260. 85760. 076 86260. 86760. 87260. 87760. 88260. 88760. 89260. 89760. 90260. 90760. 91260. 91760. 92260. 92760. 073 93260. 93760. 94260. 94760. 95260. 95760. 96260. 96760. 97260. 97760. 98260. 98760. 99260. 99760. 072 33 34 APPENDIX 2. 1. 5 to 500 keV Data (F) and uncertainties ()F) are given in barns E (eV) 2550.

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290000. 300000. 325000. 350000. 375000. 400000. 425000. 450000. 475000. 500000. 01 35 36 APPENDIX 3. 1. 4 to 800 keV The cross sections (F in barns) are the average values in the energy range E1 eV to E2 eV. The uncertainties ()F) are the statistical absolute uncertainties. 053 40 APPENDIX 4. 1. Total 235U cross section in the energy range 2 to 325 keV The cross sections (F in barns) were averaged in the energy range E1 to E2 ; a, b, c are the statistical, systematic, and total uncertainties, respectively.

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