Since 1963, when industrial waste was first injected into the subsurface in northwest Florida, considerable data have been collected relating to the geochemistry of subsurface waste storage. This report presents hydrogeologic data on two subsurface storage systems near Pensacola, Florida, both of which inject liquid industrial waste through deep wells into a saline aquifer. Injection sites are described, including details of injection and testing; geologic data from cores and grab samples; graphs of injection rates, volume, pressure, and water levels; and chemical and physical data from water-quality samples collected from injection and monitor wells.
Federal and state agencies that may have jurisdiction over various aspects of decontamination and waste disposal activities are identified in Section 2.0. Most restorative decontaminations will not require either a change in technical specification or involve an unresolved safety concern and can therefore be done without additional regulatory approvals. {a) The Pacific Northwest Laboratory is operated for the U.S. Department of Energy by Battelle Memorial Institute. v Methods of decontamination, their general effectiveness, and the advantages and disadvantages of each are outlined in Section 3.0. Dilute or concentrated chemical solutions are usually used in-situ to dissolve the contamination layer and a thin layer of the underlying substrate. Electrochemical techniques are generally limited to components but show high decontamination effectiveness with uniform corrosion. Mechani ca 1 agents are particularly appropriate for certain out-of-system surfaces and disassembled parts. These processes are catagorized and specific concerns are discussed. Good management of each phase, from planning the decontamination strategy to returning the reactor to service, is essential for an effective, safe, and efficient project. Section 4.0 stresses the planning that is necessary to manage the project, develop and implement procedures, and perform the decontamination operation. The treatment, storage, and disposal or discharge of liquid, gaseous, and solid wastes generated during the decontamination process are discussed in Section 5.0. Radioactive and other hazardous chemical wastes are considered. The environmental effects of decontamination can be minimized by monitoring emissions and instituting appropriate controls and treatment strategies. The monitoring, treatment, and control of radioactive and nonradioactive effluents, from both routine operations and possible accidents, are discussed in Section 6.0. Protecting the health and safety of personnel onsite during decontamination is of prime importance and should be considered in each facet of the decontamination process. The radiation protection philosophy of reducing exposure to levels as low as reasonably achievable should be stressed. These issues are discussed in Section 7 .0. In addition to internal and external radiation exposure control, the traditional concerns for industrial safety and hygiene should be addressed for decontamination. Personnel should be aware of specific hazards during decontamination procedures and they should be trained in emergency measures.
The accurate assessment of neutron flux and dose-rate levels in a medical environment is a topic of much current interest. In this paper, a least-squares data-analysis technique has been used for extracting neutron spectra and related information from Bonner sphere data. This technique, incorporated in the FORTRAN IV code NFLS is worthy of consideration as an alternative to the count-rate ratios and iterative-unfolding techniques used in the past. The analysis provides calculated total neutron flux density, dose-equivalent rate, and average and median-neutron-energy information as well as a plot of integral neutron-flux-density spectra. The method allows the calculation of the statistical uncertainty of each of the above quantities, which has not always been possible with other analytical methods. Results of calibration and experimental data analysis are presented and compared to results of the iterative-unfolding technique.
This report was prepared as an account of work sponsored by an agency of the United State~ Government. Ne1ther the United States Government nor any agency thereof, nor Battelle Memorial Institute, nor any or their employees, make~ any warranty, expressed or implied, or assumes any legalliabihty or respon~ibility for the accuracy, completeness, or usefulness of any 1nformat1on, apparatus, product, or process disclosed, or represents that 1ts use would not mfnnge privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherw1se does not necessarily consti• tute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof, or Battelle Memorial Institute. The views and opinions of authors expressed herein do not ncccssanly 'tate or reflect those of the Un1ted States Government or any agency thereof, or Batte lit' Memoriallnst1tute.
The discharge of radioactive materials to municipal sewer systems is regulated by the U.S. Nuclear Regulatory Commission (NRC) in accordance with 10 CFR 20, or by agreement states in accordance with state regulations. There is a need to evaluate the radiological hazard to the public resulting from release of various radionuclides into sanitary sewer systems at the maximum limits specified in 10 CFR 20. The results of a study conducted by Pacific Northwest Laboratory (PNL) for the NRC are described in this report. The generic study was conducted to evaluate potential public doses from exposure to radionuclides in sewage sludge during its treatment and disposal. This report considers release of licensee wastes apart from excreta from individuals undergoing medical diagnostic or therapeutic uses of radioactive material. A separate study will be conducted to more carefully evaluate the potential doses resulting from discharge of such patient excreta. The majority of the deterministic results from this evaluation indicated a comfortable margin between the prudently conservative estimates of annual doses and applicable permissible levels. Using Latin Hypercube sampling methods, a stochastic uncertainty and sensitivity analysis was conducted to establish potential ranges over which individual doses may vary and to identify the most sensitive parameters and assumptions used in the analysis.
scite is a Brooklyn-based organization that helps researchers better discover and understand research articles through Smart Citations–citations that display the context of the citation and describe whether the article provides supporting or contrasting evidence. scite is used by students and researchers from around the world and is funded in part by the National Science Foundation and the National Institute on Drug Abuse of the National Institutes of Health.
hi@scite.ai
10624 S. Eastern Ave., Ste. A-614
Henderson, NV 89052, USA
Copyright © 2024 scite LLC. All rights reserved.
Made with 💙 for researchers
Part of the Research Solutions Family.