Cesium chloride compatibility testing program. Annual report, fiscal year 1985
Abstract
At Hanford, fission product cesium, containing 20 to 40% /sup 137/Cs, has been recovered from the high-level waste (HLW) and converted to cesium chloride (CsCl). Recovery of the Cs, as a nitrate, from the HLW and its subsequent purification, takes place in B-Plant. Conversion of the purified product to CsCl, encapsulation of the CsCl, and water storage of the CsCl capsules takes place in the Waste Encapsulation and Storage Facility (WESF). The CsCl is doubly encapsulated in high-integrity 316L stainless steel (SS) capsules. The CsCl is loaded into the inner 316L SS capsules by melt casting. Each inner capsule, which has an ID of 2 in. (50.8 mm) and an inner length of approx.19 in. (483 mm), contains up to 3 kg of CsCl. The capsules contain up to approx.70,000 Ci of /sup 137/Cs, depending on the fission product Cs and the purity of the CsCl. To evaluate the potential hazards associated with the geologic disposal of the WESF CsCl capsules, reliable estimates of long-term attack of the capsule material by the CsCl at disposal temperatures are required. Available data on the compatibility of WESF-produced CsCl with 316L SS are not adequate for making the required evaluations. This report summarizesmore »
- Authors:
- Publication Date:
- Research Org.:
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- OSTI Identifier:
- 5907074
- Report Number(s):
- PNL-5730
ON: DE86009040; TRN: 86-013173
- DOE Contract Number:
- AC06-76RL01830
- Resource Type:
- Technical Report
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; CESIUM CHLORIDES; COMPATIBILITY; CONTAINERS; CORROSION; HIGH-LEVEL RADIOACTIVE WASTES; UNDERGROUND DISPOSAL; STAINLESS STEEL-316L; HEAT TREATMENTS; MICROSTRUCTURE; CESIUM 137; EXPERIMENTAL DATA; HIGH TEMPERATURE; IMPURITIES; METALLOGRAPHY; RADIOACTIVE WASTE DISPOSAL; RISK ASSESSMENT; ALKALI METAL COMPOUNDS; ALKALI METAL ISOTOPES; ALLOYS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CESIUM COMPOUNDS; CESIUM ISOTOPES; CHEMICAL REACTIONS; CHLORIDES; CHLORINE COMPOUNDS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; CRYSTAL STRUCTURE; DATA; HALIDES; HALOGEN COMPOUNDS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; ISOTOPES; MANAGEMENT; MATERIALS; NUCLEI; NUMERICAL DATA; ODD-EVEN NUCLEI; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; RADIOISOTOPES; STAINLESS STEELS; STEELS; WASTE DISPOSAL; WASTE MANAGEMENT; WASTES; YEARS LIVING RADIOISOTOPES; 360105* - Metals & Alloys- Corrosion & Erosion; 052002 - Nuclear Fuels- Waste Disposal & Storage; 360102 - Metals & Alloys- Structure & Phase Studies
Citation Formats
Bryan, G H. Cesium chloride compatibility testing program. Annual report, fiscal year 1985. United States: N. p., 1986.
Web. doi:10.2172/5907074.
Bryan, G H. Cesium chloride compatibility testing program. Annual report, fiscal year 1985. United States. https://doi.org/10.2172/5907074
Bryan, G H. 1986.
"Cesium chloride compatibility testing program. Annual report, fiscal year 1985". United States. https://doi.org/10.2172/5907074. https://www.osti.gov/servlets/purl/5907074.
@article{osti_5907074,
title = {Cesium chloride compatibility testing program. Annual report, fiscal year 1985},
author = {Bryan, G H},
abstractNote = {At Hanford, fission product cesium, containing 20 to 40% /sup 137/Cs, has been recovered from the high-level waste (HLW) and converted to cesium chloride (CsCl). Recovery of the Cs, as a nitrate, from the HLW and its subsequent purification, takes place in B-Plant. Conversion of the purified product to CsCl, encapsulation of the CsCl, and water storage of the CsCl capsules takes place in the Waste Encapsulation and Storage Facility (WESF). The CsCl is doubly encapsulated in high-integrity 316L stainless steel (SS) capsules. The CsCl is loaded into the inner 316L SS capsules by melt casting. Each inner capsule, which has an ID of 2 in. (50.8 mm) and an inner length of approx.19 in. (483 mm), contains up to 3 kg of CsCl. The capsules contain up to approx.70,000 Ci of /sup 137/Cs, depending on the fission product Cs and the purity of the CsCl. To evaluate the potential hazards associated with the geologic disposal of the WESF CsCl capsules, reliable estimates of long-term attack of the capsule material by the CsCl at disposal temperatures are required. Available data on the compatibility of WESF-produced CsCl with 316L SS are not adequate for making the required evaluations. This report summarizes the program activities for FY 1985. 3 refs., 7 figs., 2 tabs.},
doi = {10.2172/5907074},
url = {https://www.osti.gov/biblio/5907074},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat Mar 01 00:00:00 EST 1986},
month = {Sat Mar 01 00:00:00 EST 1986}
}