Analytical radiation shielding calculations for concrete — formulas and parameters
Tài liệu tham khảo
Hilsdorf, 1967, The water content of hardened concrete, Nucl. Radiation Shielding Studies Report No. 4, DASA 1875
Schmidt, 1969
Price, 1957
Broder, 1964, Effect of water content in concrete on thickness and cost of reactor shielding, Sov. J. At. Energy, 16, 26, 10.1007/BF01131718
Trubey, 1966, A survey of empirical functions used to fit gamma ray buildup factors, ORNL-RSIC-10
Stevens, 1968, Methods of calculating neutron and gamma ray attenuation
Berger, 1956, 47
Zoller, 1964, Fast-neutron-removal cross sections, Nucleonics, 22, 128
Walker, 1961, A summary of shielding constants for concrete, ANL-6443
Bunch, 1965, Shielding properties of various concretes as a function of temperature, Transactions of the American Nuclear Society, 8, 182
1968
1963, ANL-5800
Drake, 1967, Neutron and gamma-ray production cross-sections for sodium, magnesium, chlorine, potassium and calcium, NDL-TR-89, Vol. I–VI
Schmidt, 1966, Neutron cross sections for fast reactor materials, Part I, Evaluation, KFK 120
Penny, 1966, OGRE, a Monte CArlo system for gamma-ray transport studies, including an example (OGRE-P1) for transmission through laminated slabs, ORNL-3805
Bartholomew, 1967, Compendium of thermal-neutron-capture gamma ray measurements, Part I, Z ⩽ 46, Nuclear Data, A3, 367, 10.1016/S0550-306X(67)80014-4
Bartholomew, 1969, Compendium of thermal-neutron-capture gamma ray measurements, Part III, Z = 68–94, Nuclear Data, A5, 243
Maerker, 1968, Gamma ray spectra arising from thermal-neutron capture in iron, aluminum and copper, Transactions of the American Nuclear Society, 11, 701
Maerker, 1969, Gamma ray spectra arising from thermal-neutron capture in iron, aluminum and copper, ORNL-4382, 11
K.J.Yost, DUCAL, a code for the calculation of gamma-ray production cross-sections, ORNL-4165 (to be published).
Claiborne, 1969, Transactions of the American Nuclear Society, 12, 383
Claiborne, 1969, ORNL-TM-2574