Review of iodine behavior from nuclear fuel dissolution to environmental release
During nuclear fuel reprocessing, radioiodine, can be released.
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Engineering topics
Tingey, Joel M.
Publications and source records attributed to Tingey, Joel M..
Synthesis of Plutonium Oxide Specimens for a Statistically Designed Nuclear Forensics Study
This report describes the synthesis of plutonium oxide (PuO 2 ) samples at a bench-scale (10 g Pu) to support nuclear forensics research. The key unit operations that were performed included dissolving the PuO 2 feed material, purifying the Pu by ion exchange, precipitating as plutonium (III) oxalate, and reconverting to PuO 2 by calcination of the oxalate compound. Seventy-six PuO 2 synthetic runs were performed in execution of a statistically designed test matrix. The process parameters varied in these synthesis runs included temperature (30 or 50 °C), the Pu concentration in the feed solution (10, 30, or 50 g Pu/L), the HNO 3 concentration in the feed solution (1, 2, or 3 M), the direction of reagent addition (direct or reverse strike), the source of oxalic acid (solid or solution), and the reagent addition rate (as fast as possible, 20, or 40 minutes). This report describes the synthesis of the 76 PuO 2 specimens. The characterization of these specimens will be described in separate reports.
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗
A Workshop on the History of Plutonium Processing at Hanford Washington as the Foundation for Modern-day Plutonium Process Science
Numerous national laboratories in the United States have roots related to the Manhattan Project that contributed to the end of World War II. The pioneering science and engineering that took place over the decades that followed continues to influence modern-day actinide-related research at those institutions, leading to unique strengths and cutting-edge ideas and perspectives. These same national laboratories also face a challenge: figuring out how to capture the expertise of a retiring workforce who had first-hand experience in these pioneering nuclear efforts. Recently, at PNNL a “Train-the-Trainer” approach has been piloted where mentors and mentees are paired together to develop and deliver interactive workshops on historical topics that relate to modern-day research, such as Plutonium Processing or Environmental Management of Legacy Nuclear Waste. This approach was used to develop a workshop that beings with the Historic Hanford process plutonium chemistry and engineering, describes its influence on current plutonium separation and process science, and then details the chemistry of plutonium as it progresses from a minor constituent in irradiated fuel to purified solid product. This workshop is targeted to the practitioner of applied science and technology wishing to gain a better understanding of the history and process-related chemistry of element 94 so that they may better direct the tools of their specific craft toward the present and future needs of plutonium science.
Smith, Frances N.↗
Facility Modeling Capability Demonstration Summary Report
A joint effort has been initiated by Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Savanah River National Laboratory (SRNL), Pacific Northwest National Laboratory (PNNL), sponsored by the National Nuclear Security Administration’s (NNSA’s) office of Proliferation Detection, to develop and validate a flexible framework for simulating effluents and emissions from spent fuel reprocessing facilities. These effluents and emissions can be measured by various on-site and/or off-site means, and then the inverse problem can ideally be solved through modeling and simulation to estimate characteristics of facility operation such as the nuclear material production rate. The flexible framework called Facility Modeling Toolkit focused on the forward modeling of PUREX reprocessing facility operating conditions from fuel storage and chopping to effluent and emission measurements.
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Sampling Tools for Contaminated Hot Cells and Remotely Accessed Tanks
The U.S. Department of Energy (DOE) and the Pacific Northwest National Laboratory in collaboration with the Andronikashvili Institute of Physics in Tbilisi, Georgia have developed and tested technologies which sample contaminated areas inside hot cell facilities. Sampling locations in the facility include drains, ventilation exhaust ducts, sumps and shielded waste tanks. Tool designs for sampling each location include the ability to introduce the tool using existing ports, pass-throughs or inter-cells trolley and operate the tool with the existing remote manipulators. Areas inside the hot cell facility that would likely be contaminated from chemically processing irradiated reactor targets and fuel even after decontamination have been identified as potential sampling locations. Andronikashvili Institute of Physics in Tbilisi, Georgia has access to a reactor, hot cells, glove boxes and storage facilities that have been used to develop and test hot cell sampling technologies. These facilities are uncontaminated with radiological material and provide the ability to test these sampling technologies on representative equipment without contaminating the tools. Prototype tools have been fabricate and tested at these facilities using simulants representative of radiological contamination and waste.
Rostomashvili, Z.↗
Design of the Laboratory-Scale Plutonium Oxide Processing Unit in the Radiochemical Processing Laboratory
This report describes a design for a laboratory-scale capability to produce plutonium oxide (PuO 2 ) for use in identifying and validating nuclear forensics signatures associated with plutonium production, as well as for use as exercise and reference materials. This capability will be located in the Radiochemical Processing Laboratory at the Pacific Northwest National Laboratory. The key unit operations are described, including PuO 2 dissolution, purification of the Pu by ion exchange, precipitation, and re-conversion to PuO 2 by calcination.
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗
Conceptual Design for the Pilot-Scale Plutonium Oxide Processing Unit in the Radiochemical Processing Laboratory
This report describes a conceptual design for a pilot-scale capability to produce plutonium oxide for use as exercise and reference materials, and for use in identifying and validating nuclear forensics signatures associated with plutonium production. This capability is referred to as the Pilot-scale Plutonium oxide Processing Unit (P3U), and it will be located in the Radiochemical Processing Laboratory at the Pacific Northwest National Laboratory. The key unit operations are described, including plutonium dioxide (PuO2) dissolution, purification of the Pu by ion exchange, precipitation, and conversion to oxide by calcination.
plutonium oxide↗
Plutonium Oxide Process Capability Work Plan
Pacific Northwest National Laboratory (PNNL) has been tasked to develop a Pilot-scale Plutonium-oxide Processing Unit (P3U) providing a flexible capability to produce 200g (Pu basis) samples of plutonium oxide using different chemical processes for use in identifying and validating nuclear forensics signatures associated with plutonium production. Materials produced can also be used as exercise and reference materials.
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