Quality Assurance System for Collection and Check of Radioactive Waste

Author(s):  
Gheorghe C. Dogaru

Abstract A component of the quality assurance system applied at Radioactive Waste Treatment Plant refers to the collection, identification and characterisation of radioactive waste including spent sealed radioactive sources before their treatment and conditioning. One of the most important challenges to be solved is to apply this procedure to the collection and characterisation of the “historical” radioactive waste for which is not recorded and no analyse bulletin for characterisation and identification is existing. The procedure “Collection and characterization of radioactive waste” applied at the Radioactive Waste Treatment Plant is based on regulatory requirements concerning collection, characterization and identification of all radioactive materials including sealed spent radioactive sources.

Author(s):  
Gheorghe Barariu

This paper presents the design criteria and the prerequisites for the development of the Radioactive Waste Treatment Plant - RWTP which will comply with L/ILW Final Repository requirements to be built near Cernavoda NPP. The RWTP will be designed to satisfy the main performance objectives in accordance to IAEA recommendation and on basis of the Repository’s Waste Acceptance Criteria resulted from the local conditions. One of the most important technological aspect is related to the selection of technologies, which implies, on the one hand, the impact on present generation respectively incineration, radwaste transfer from the SS drums to CS drums, SS drums super compaction and spent filter cartridges cutting, and on the other hand, technologies that isolate for 300 years the tritium and C-14 in the Repository with impact for the next generations. The Saligny Repository will be commissioned in 2014 and in order to accept radwastes from Cernavoda NPP it is necessary that the radwastes are suitably treated for long–term radionuclides isolation. The conditions and requirements including many uncertainties and constraints reduce the possibilities to select the suitable treatment technologies for the Waste Treatment Plant designed for the radwastes generated by Cernavoda NPP, this selection being a critical case due to the limited storage capacity of existing Radioactive Waste Storage Facility. The necessary Radioactive Waste Treatment Plant implies a detailed analysis including ethical aspects of the selected technologies.


Author(s):  
Brigette Rosendall ◽  
Chris Barringer ◽  
Feng Wen ◽  
Kelly J. Knight

The Columbia River in Washington State is threatened by the radioactive legacy of the cold war. Two hundred thousand cubic meters (fifty-three million US gallons) of radioactive waste is stored in 177 underground tanks (60% of the Nation’s radioactive waste). A vast complex of waste treatment facilities is being built to convert this waste into stable glass (vitrification). The waste in these underground tanks is a combination of sludge, slurry, and liquid. The waste will be transported to a pre-treatment facility where it will be processed before vitrification. It is necessary to keep the solids in suspension during processing. The mixing devices selected for this task are known as pulse-jet mixers (PJMs). PJMs cyclically empty and refill with the contents of the vessel to keep it mixed. The transient operation of the PJMs has been proven successful in a number of applications, but needs additional evaluation to be proven effective for the slurries and requirements at the Waste Treatment Plant (WTP). Computational fluid dynamic (CFD) models of mixing vessels have been developed to demonstrate the ability of the PJMs to meet mixing criteria. Experimental studies have been performed to validate these models. These tests show good agreement with the transient multiphase CFD models developed for this engineering challenge.


Author(s):  
T. Bond Calloway ◽  
Christopher J. Martino ◽  
Carol M. Jantzen ◽  
William R. Wilmarth ◽  
Michael E. Stone ◽  
...  

Evaporation of High Level and Low Activity (HLW & LAW) radioactive wastes for the purposes of radionuclide separation and volume reduction has been conducted at the Savannah River and Hanford Sites for more than forty years. Additionally, the Savannah River Site (SRS) has used evaporators in preparing HLW for immobilization into a borosilicate glass matrix. The Hanford River Protection Project (RPP) is in the process of building the world’s largest radioactive waste treatment facility, Waste Treatment Plant (WTP), which will use evaporators to concentrate the liquid waste and plant recycles prior to immobilization into a borosilicate glass matrix. Radioactive waste is evaporated at each site using various evaporator designs (e.g., forced circulation, horizontal bent tube). While the equipment used to evaporate radioactive waste is relatively simple in design, the complexity in the evaporator processes in current service and in those currently in the design stages stems from the heterogeneous nature of the waste and the effects of seemingly minor components (e.g., Si) on the process. Aqueous electrolyte thermodynamic modeling and experiments have been conducted by the SRS Savannah River Technology Center (SRTC) in support of the SRS HLW and Defense Waste Processing Facility (DWPF) Evaporators and the Hanford RPP WTP. After 40 years of successful operation, accumulation of two solid phases (a nitrated aluminosilicate, Na8AL6Si6O24(NO3)2•4H2O and sodium diuranate, Na2U2O7) developed as an insoluble phase in the Savannah River Site (SRS) 2H evaporator in 1996. The aluminosilicate scale deposit caused the SRS 2-H evaporator to become completely inoperable by October 1999. Accumulation of the sodium diuranate phase on the aluminosilicate scale has caused criticality concerns. Modeling and experiments were conducted to develop a method to control the process chemistry in order to prevent the formation of aluminosilicate deposits in the future. The lessons learned from the development, design, and operation of the SRS waste treatment facilities and the currently operating 242-A Hanford HLW evaporators were applied by SRTC in support of the development and design of the Hanford WTP evaporators. Thermodynamic equilibrium modeling along with solubility and physical property experiments are being conducted to develop process control and flow sheet models. Additionally, lessons learned from the development of an advanced antifoam agent for the SRS vitrification process evaporators are being applied to the testing and development of an antifoam agent for the Hanford WTP evaporators. This paper will discuss the methodologies, results, and achievements of the SRTC evaporator development program that was conducted in support of the SRS and Hanford WTP evaporator processes. The “cross-pollination” and application of waste treatment technologies and methods between the Savannah River and Hanford Sites will be highlighted. The “cross-pollination” of technologies and methods is expected to benefit the Department of Energy’s Mission Acceleration efforts by reducing the overall cost and time for the development of the baseline waste treatment processes.


Author(s):  
Satoshi Yanagihara ◽  
Mitsuo Tachibana ◽  
Taro Shimada ◽  
Takenori Sukegawa ◽  
Kunio Shiraishi

Abstract In the Japan Power Demonstration Reactor (JPDR) decommissioning project, the procedure for clean-up activities was specially studied for harmonization with radioactive waste treatment policy in Japan; it consisted of several components such as survey of the facility operational history, radiological characterization of building surfaces, decontamination and final survey of radioactivities. After confirming that there was no significant radioactivity in the facilities in the final step of the procedure, buildings were demolished in consideration of treatment of wastes as non-radioactive materials. The JPDR decommissioning project was completed by March 1996 with no serious problems, which showed that the procedure was rational, and that the experiences are useful for planning of future decommissioning activities. The dismantling and clean-up activities were reviewed, and the experiences are excepted to contribute to establishing standard and regulatory systems on decommissioning nuclear facilities.


2021 ◽  
Author(s):  
Jingyi Shen ◽  
Zonghuan Chen ◽  
Bingheng Wang ◽  
Guiling Gao

Abstract In high-level waste treatment plants, rooms where the highly radioactive sources (such as the vitrification containers) are operated have high radiation protection risk. On the purpose of ensuring the safety of operators, it is necessary to design corresponding shielding walls, windows and shielding doors to guarantee that the dose rate at the personal operating location outside the room meets corresponding control requirements. Compared with walls, the radiation safety designs of the doors and windows are more complicated. In this article, a shielding door of a hot room inside a high-level waste treatment plant is selected. By means of combing the source characteristics and the source location, the gap between the door and door frame as well as the lap joints of the door and the wall are analyzed in order to characterize the influence factor of the dose rate outside the shielding door. The results illustrate that, under the premise that the shielding design requirements are satisfied, the lap joint between shielding wall and door has a significant impact on the outdoor dose field due to the oblique incidence of the radiation ray. Therefore, in the follow-up design of the radiation shielding door, A certain overlap form of the lap joints between the door and the wall need to be satisfied, furthermore, special attention need to be paid to the shielding of radioactive sources with weak self-shielding effect and strong penetration ability, for ensuring the shielding door to the greatest extent radiation protection ability.


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