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Aldrich, D.C.; Ericson, D.M. Jr.
Massachusetts Inst. of Tech., Cambridge (USA). Dept. of Nuclear Engineering; Sandia Labs., Albuquerque, N.Mex. (USA)1978
Massachusetts Inst. of Tech., Cambridge (USA). Dept. of Nuclear Engineering; Sandia Labs., Albuquerque, N.Mex. (USA)1978
AbstractAbstract
[en] A multicompartment ventilation model has been presented for the calculation of airborne radioactive material concentrations internal to structures. The model was used to estimate the potential effectiveness of sheltering in reducing the dose due to inhaled radionuclides. The sensitivity of the model to parameter values and protection strategies was discussed. Using ''best estimate'' values for the model parameters, this analysis indicated that sheltered individuals received a reduction of 35 percent in the dose from inhaled radionuclides. Larger reductions would be possible if lower values of the ventilation rate n, could be achieved by either tighter building construction or emergency sealing of openings in the structure. Such emergency means could include taping windows, placing wet paper over cracks, etc. Further analysis indicated that the strategy of opening doors and windows, turning on ventilating systems, etc., in an attempt to ''air-out'' the structure after the cloud of radioactive material had passed will most likely not contribute significantly to reduction in dose due to inhaled radionuclides unless very low initial ventilation rates are achieved. Although the available data did not allow quantitative predictions of dose reductions afforded by basements or other appropriately sealed-off rooms, preliminary analysis indicated qualitatively that they could be significant
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Jan 1978; 47 p; Available from NTIS., PC A03/MF A01
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