ANALYSIS OF THE SALT FEED TANK CORE SAMPLE

Reigel, M. ; Cheng, W.

关键词: AR FACILITIES;    BUILDUP;    CESIUM 137;    CHROMIUM;    GROUTING;    HAZARDOUS MATERIALS;    LIQUID WASTES;    LOW-LEVEL RADIOACTIVE WASTES;    MERCURY;    MONITORING;    PERFORMANCE;    PROCESSING;    RADIOACTIVE MATERIALS;    RADIOACTIVE WASTE STORAGE;    RADIOISOTOPES;    SAMPLERS;    SAVANNAH RIVER PLANT;    TANKS;    WASTES;    WATER;   

DOI  :  10.2172/1036734
RP-ID  :  SRNL-TR-2011-00326
PID  :  OSTI ID: 1036734
Others  :  TRN: US1201522

学科分类：核能源与工程

美国|英语

来源: SciTech Connect

【 摘 要 】

The Saltstone Production Facility (SPF) immobilizes and disposes of low-level radioactive and hazardous liquid waste (salt solution) remaining from the processing of radioactive material at the Savannah River Site (SRS). Low-level waste (LLW) streams from processes at SRS are stored in Tank 50 until the LLW can be transferred to the SPF for treatment and disposal. The Salt Feed Tank (SFT) at the Saltstone Production Facility (SPF) holds approximately 6500 gallons of low level waste from Tank 50 as well as drain water returned from the Saltstone Disposal Facility (SDF) vaults. Over the past several years, Saltstone Engineering has noted the accumulation of solids in the SFT. The solids are causing issues with pump performance, agitator performance, density/level monitoring, as well as taking up volume in the tank. The tank has been sounded at the same location multiple times to determine the level of the solids. The readings have been 12, 25 and 15 inches. The SFT is 8.5 feet high and 12 feet in diameter, therefore the solids account for approximately 10 % of the tank volume. Saltstone Engineering has unsuccessfully attempted to obtain scrape samples of the solids for analysis. As a result, Savannah River National Laboratory (SRNL) was tasked with developing a soft core sampler to obtain a sample of the solids and to analyze the core sample to aid in determining a path forward for removing the solids from the SFT. The source of the material in the SFT is the drain water return system where excess liquid from the Saltstone disposal vaults is pumped back to the SFT for reprocessing. It has been shown that fresh grout from the vault enter the drain water system piping. Once these grout solids return to the SFT, they settle in the tank, set up, and can't be reprocessed, causing buildup in the tank over time. The composition of the material indicates that it is potentially toxic for chromium and mercury and the primary radionuclide is cesium-137. Qualitative measurements show that the material is not cohesive and will break apart with some force.