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Title: Testing and Analysis of Consolidated Sludge Samples from the 105 K East Basin Floor and Canisters

Abstract

The testing reported here was performed on K East Basin consolidated sludge samples to generate data needed for the evaluation and design of the systems that will be used to disposition the K Basin sludge to T-Plant for interim storage. The tests were conducted by Pacific Northwest National Laboratory from May through November 1999 under the direction of the Spent Nuclear Fuel (SNF) Project. The samples used in the work discussed here were collected by the SNF Characterization Project from the KE Basin floor and canisters during March and April 1999. These samples (3 from the floor and 3 from the canisters) were shipped to the storage pool at the Postirradiation Testing Laboratory (327 Building) and later transferred to the PNNL Radiochemical Processing Laboratory (325 Building), where they were recovered for testing and analysis. Testing activities presented in this report include particle size measurement via wet sieving, sludge settling and sludge density measurements, sludge shear strength measurement, and measurement of sludge dissolution enthalpy to ascertain the uranium metal content of the sludge. Section 1.0 provides the summary and conclusions to date. Section 2.0 describes the consolidated sample container system, the sample collection and transfer, inspection, and recovery of the samplesmore » for testing. Section 3.0 describes the testing methodologies and presents the results and analyses.« less

Authors:
 [1];  [1];  [1];  [1]
  1. BATTELLE (PACIFIC NW LAB)
Publication Date:
Research Org.:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
15003683
Report Number(s):
PNNL-13341
820201000; TRN: US1005069
DOE Contract Number:  
AC06-76RL01830
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; CONTAINERS; DESIGN; DISSOLUTION; ENTHALPY; EVALUATION; FLOORS; NUCLEAR FUELS; PARTICLE SIZE; PROCESSING; SLUDGES; STORAGE; TESTING; URANIUM; WASTE STORAGE; consolidated sludge, K East Basin, canister, floor, sieving, density, shear strength

Citation Formats

Bredt, Paul R, Delegard, Calvin H, Schmidt, Andrew J, and Silvers, Kurt L. Testing and Analysis of Consolidated Sludge Samples from the 105 K East Basin Floor and Canisters. United States: N. p., 2000. Web. doi:10.2172/15003683.
Bredt, Paul R, Delegard, Calvin H, Schmidt, Andrew J, & Silvers, Kurt L. Testing and Analysis of Consolidated Sludge Samples from the 105 K East Basin Floor and Canisters. United States. https://doi.org/10.2172/15003683
Bredt, Paul R, Delegard, Calvin H, Schmidt, Andrew J, and Silvers, Kurt L. Mon . "Testing and Analysis of Consolidated Sludge Samples from the 105 K East Basin Floor and Canisters". United States. https://doi.org/10.2172/15003683. https://www.osti.gov/servlets/purl/15003683.
@article{osti_15003683,
title = {Testing and Analysis of Consolidated Sludge Samples from the 105 K East Basin Floor and Canisters},
author = {Bredt, Paul R and Delegard, Calvin H and Schmidt, Andrew J and Silvers, Kurt L},
abstractNote = {The testing reported here was performed on K East Basin consolidated sludge samples to generate data needed for the evaluation and design of the systems that will be used to disposition the K Basin sludge to T-Plant for interim storage. The tests were conducted by Pacific Northwest National Laboratory from May through November 1999 under the direction of the Spent Nuclear Fuel (SNF) Project. The samples used in the work discussed here were collected by the SNF Characterization Project from the KE Basin floor and canisters during March and April 1999. These samples (3 from the floor and 3 from the canisters) were shipped to the storage pool at the Postirradiation Testing Laboratory (327 Building) and later transferred to the PNNL Radiochemical Processing Laboratory (325 Building), where they were recovered for testing and analysis. Testing activities presented in this report include particle size measurement via wet sieving, sludge settling and sludge density measurements, sludge shear strength measurement, and measurement of sludge dissolution enthalpy to ascertain the uranium metal content of the sludge. Section 1.0 provides the summary and conclusions to date. Section 2.0 describes the consolidated sample container system, the sample collection and transfer, inspection, and recovery of the samples for testing. Section 3.0 describes the testing methodologies and presents the results and analyses.},
doi = {10.2172/15003683},
url = {https://www.osti.gov/biblio/15003683}, journal = {},
number = ,
volume = ,
place = {United States},
year = {2000},
month = {11}
}