Drying Results of K-Basin Damaged/Corroded SNF Internal Sludge and Surface Coating

Abrefah, J. ; Alexander, D.L. ; Marschman, S.C.

Pacific Northwest National Laboratory (U.S.)

关键词: Sludges;    Heating;    Pressurization;    Fuel Storage Pools;    N-Reactor;   

DOI  :  10.2172/763030
RP-ID  :  PNNL-11932
RP-ID  :  AC06-76RL01830
RP-ID  :  763030

美国|英语

来源: UNT Digital Library

【 摘 要 】

Experiments were performed using a thermogravimetric analysis (TGA) system by Pacific Northwest National Laboratory (PNNL)to study the drying behavior of the K-Basin spent nuclear fuel (SNF) internal sludge and two different surface coatings of SNF elements. These measurements were conducted in support of the safety and process analyses of the proposed Integrated Process Strategy (IPS) to move the N-Reactor fuel stored at K-Basin to an interim storage facility. These limited experiments on the corrosion products of K-Basin SNF material were part of the broad studies performed to ascertain the bounding pressurization of the Multi-Canister Overpack (MCO). Seven SNF internal sludge samples taken from different damage regions of three damaged/corroded outer K-Basin SNF elements were dried. Additionally, two surface coating samples taken from two SNF elements stored at K-West were tested. All the tests were performed in a vacuum atmosphere with the same temperature ramp rate of about 0.4 C/ min. Each TGA test sample was weighed before and after the test on a balance located in the Shielded Analytical Laboratory hot cell. The test samples were vacuum dried in the TGA system for about 24 hours prior to heating them at the rate of 0.4 C/min. The observations from the weight change data are summarized below.