45-Day safety screen results for tank 241-U-203, push mode, cores 79 and 80
Abstract
Two one-segment core samples from tank 241-U-203 (U-203) were received by the 222-S Laboratories and underwent safety screening analysis, consisting of differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), and total alpha activity. In addition to the safety screening requirements, inductively coupled plasma (ICP) spectrographic analysis for lithium was performed to determine the extent of hydrostatic head fluid contamination during the sampling event. No notification limits were exceeded for these analyses.
- Authors:
- Publication Date:
- Research Org.:
- Westinghouse Hanford Co., Richland, WA (United States)
- Sponsoring Org.:
- USDOE, Washington, DC (United States)
- OSTI Identifier:
- 74107
- Report Number(s):
- WHC-SD-WM-DP-109
ON: DE95012837; TRN: 95:016343
- DOE Contract Number:
- AC06-87RL10930
- Resource Type:
- Technical Report
- Resource Relation:
- Other Information: PBD: 5 May 1995
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 05 NUCLEAR FUELS; HANFORD RESERVATION; TANKS; DRILL CORES; CALORIMETRY; THERMAL GRAVIMETRIC ANALYSIS; EXPERIMENTAL DATA; LITHIUM; ALPHA-BEARING WASTES; HIGH-LEVEL RADIOACTIVE WASTES; RADIOACTIVE WASTE MANAGEMENT
Citation Formats
Schreiber, R D. 45-Day safety screen results for tank 241-U-203, push mode, cores 79 and 80. United States: N. p., 1995.
Web. doi:10.2172/74107.
Schreiber, R D. 45-Day safety screen results for tank 241-U-203, push mode, cores 79 and 80. United States. https://doi.org/10.2172/74107
Schreiber, R D. 1995.
"45-Day safety screen results for tank 241-U-203, push mode, cores 79 and 80". United States. https://doi.org/10.2172/74107. https://www.osti.gov/servlets/purl/74107.
@article{osti_74107,
title = {45-Day safety screen results for tank 241-U-203, push mode, cores 79 and 80},
author = {Schreiber, R D},
abstractNote = {Two one-segment core samples from tank 241-U-203 (U-203) were received by the 222-S Laboratories and underwent safety screening analysis, consisting of differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), and total alpha activity. In addition to the safety screening requirements, inductively coupled plasma (ICP) spectrographic analysis for lithium was performed to determine the extent of hydrostatic head fluid contamination during the sampling event. No notification limits were exceeded for these analyses.},
doi = {10.2172/74107},
url = {https://www.osti.gov/biblio/74107},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri May 05 00:00:00 EDT 1995},
month = {Fri May 05 00:00:00 EDT 1995}
}
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