Determination of the radioactive material and plutonium holdup in ducts and piping in the 325 Building

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This report describes the measurements performed to determine the radionuclide content and mass of Pu in exposed ducts, filters, and piping in the 325 Building at the Hanford Site. This information is needed to characterize facility radiation levels, to verify compliance with criticality safety specifications, and to allow more accurate nuclear material control using nondestructive assay. Gamma assay was used to determine the gamma-emitting isotopes in ducts, filters, and piping. Passive neutron counting was used to estimate the Pu content. A high-purity Ge detector and a neutron slab detector containing 5 {sup 3}He proportional counters were used. Almost all the … continued below

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103 p.

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Haggard, D. L.; Tanner, J. E. & Tomeraasen, P. L. August 1, 1996.

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Description

This report describes the measurements performed to determine the radionuclide content and mass of Pu in exposed ducts, filters, and piping in the 325 Building at the Hanford Site. This information is needed to characterize facility radiation levels, to verify compliance with criticality safety specifications, and to allow more accurate nuclear material control using nondestructive assay. Gamma assay was used to determine the gamma-emitting isotopes in ducts, filters, and piping. Passive neutron counting was used to estimate the Pu content. A high-purity Ge detector and a neutron slab detector containing 5 {sup 3}He proportional counters were used. Almost all the gamma activity is from {sup 137}Cs and {sup 60}Co. Estimated Pu mass gram equivalents in the basement ductwork and filters are 31 g; the radioactive liquid waste system (RLWS) line has 12 g; the laboratory vacuum system has 2 g equiv. Pu; the retention process sewer has 3 g. Total Pu mass holdup for basement areas range from 48 to 27 g. Estimated Pu mass gram equivalents for all laboratories range from 385 to 581 g. Individual laboratory estimates are tabulated. Total estimated Pu gram equivalent holdup and material in process for the facility is 410 g. In summary, results indicate that no significant Pu levels, from a criticality safety perspective, reside in the ductwork, laboratory vacuum system lines, RLWS pipes, or any one laboratory in the 325 Building.

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103 p.

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INIS; OSTI as DE96050428

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  • Other Information: PBD: Aug 1996

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  • August 1, 1996

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Haggard, D. L.; Tanner, J. E. & Tomeraasen, P. L. Determination of the radioactive material and plutonium holdup in ducts and piping in the 325 Building, report, August 1, 1996; Richland, Washington. (https://digital.library.unt.edu/ark:/67531/metadc679021/: accessed July 16, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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