1959
DOI: 10.1097/00004032-195904000-00001
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Accidental Radiation Excursion at the Oak Ridge Y-12 Plant—III

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Cited by 37 publications
(16 citation statements)
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“…Eight Y-12 employees, who did not have a notable potential for exposure to neutrons or gamma rays and were not wearing a film badge dosimeter, received estimated radiation doses ranging from 23 rem to 365 rem (Hurst, Ritchie, and Emerson 1959). As a result of this criticality accident at the Y-12 Plant, a newer dosimeter system was developed that was an integral part of each employee's ID badge and contained components for both routine and accident-related dosimetry (Thornton, Davis and Gupton 1961, pp.…”
Section: Neutron Film Badge Dosimetry At Y-12 Facilitiesmentioning
confidence: 99%
“…Eight Y-12 employees, who did not have a notable potential for exposure to neutrons or gamma rays and were not wearing a film badge dosimeter, received estimated radiation doses ranging from 23 rem to 365 rem (Hurst, Ritchie, and Emerson 1959). As a result of this criticality accident at the Y-12 Plant, a newer dosimeter system was developed that was an integral part of each employee's ID badge and contained components for both routine and accident-related dosimetry (Thornton, Davis and Gupton 1961, pp.…”
Section: Neutron Film Badge Dosimetry At Y-12 Facilitiesmentioning
confidence: 99%
“…Total linear attenuation coefficient, 3-35, 3-36, 3-37, 3-42 Total macroscopic cross section, E, 3-52, 3-53, 3-54, 8-26 Total microscopic cross section, at, 3-51, 3-52 Toxicity (toxic), [16][17][18][19][20][21][22][23][24][25][26][27][28][29][30][31][32][33][17][18][19][20][21][22][23][24][25][26][27][28][29][30][31][32][33][34][35][36][16][17][18][19][20][21][22][23][24][25][26][27][28][29][13][14][15]…”
Section: -16mentioning
confidence: 99%
“…Accordingly, among the radioisotopes, activated sodium, 24 Na, in human body or a blood sample was utilized to evaluate dose in some past accidents. [2][3][4] Although the dose assessment in the past events indicated advantages of this technique, the dose evaluation in the Tokai-mura criticality accident revealed that some data were quite essential to obtain dose rapidly based upon activated sodium in body. 2) In the previous study, 5) Monte Carlo calculations using the MCNP-4B 6) code had derived quantitative relations between specific activity of 24 Na induced in soft tissue and dose to whole body with the MIRD-5 type phantom 7) for external neutrons from some hypothesized criticality systems.…”
Section: Introductionmentioning
confidence: 99%