Immobilization of Organic Liquid Radioactive Waste (LWR) in a Sulfur Composite Matrix at the BN-350 Fast Neutron Reactor Site, Kazakhstan - 18031
- Pacific Nuclear Solutions (United States)
- Nuclear Engineering Division, Argonne National Laboratory (United States)
The immobilization treatment and final disposition of all forms of organic radioactive liquids, such as pump oil, spent solvent, tri-butyl-phosphate (TBP) and scintillation fluids, remain a significant challenge for nuclear waste generators and national regulators. The majority of nuclear nations have instituted regulations that require some form of encapsulation of treated organic liquid, notwithstanding LLW organic liquids that can be safely incinerated. In most cases cement is the designated material for encapsulation; however, cement can pose certain problems with the containment of treated organic liquids. In 2013, with funding from the U.S. Department of Energy - National Nuclear Security Administration through its Global Initiative for Proliferation Prevention Program (GIPP), a proven U.S. technology for the treatment of radioactive organic liquids was introduced at the BN-350 fast neutron reactor facility in Aktau, Kazakhstan. As the facility was undergoing full decommissioning, one hundred and sixty cubic meters of contaminated pump oil (including Cs-137, Sr-90 and U-235/238) contained in large above ground tanks had to be treated for final disposal. As a result of the research conducted over a two-year period, a new 2-step treatment process was invented by combining the U.S. solidification technology with a newly developed inorganic filler and molecular sulfur, referred to as radiation-resistant composite (RRC) to fully encapsulate the waste oil. The outcome of extensive test program indicates that the final form can reach up to 60 wt.% with a compressive strength of about 100 kg/cm{sup 2}. Preliminary conclusions indicate that RRC outperforms cement as an encapsulation form for final waste treatment which meets U.S. Nuclear Regulatory requirements for final disposal. This paper examines the preliminary experimental work that was conducted in Kazakhstan with the U.S. polymer technology and radioactive pump oil, and the subsequent secondary process of combining the solidified material into a homogeneous final form utilizing RRC. Topics covered in the paper include: - Kazakhstan's regulatory requirements for attaining an achievable waste form for acceptance, which led to the RRC invention; - Technical objectives for the application of polymer technology and RRC materials to radioactive liquid waste; - Polymer solidification with radioactive oil and the result; step one of the RRC process; - Description of RRC materials, their origin and chemical characteristics; - Process of combining the solidified polymer mass with RRC materials into a solid, homogeneous matrix; step two of the RRC process; - Experimental results including leaching data, waste loading estimates and heat process calculations to create the matrix; - Cost advantages of the RRC process over cementation; - Limitations of the RRC process; - Next steps to verify conformance of the RRC technology to the U.S. requirements. (authors)
- Research Organization:
- WM Symposia, Inc., PO Box 27646, 85285-7646 Tempe, AZ (United States)
- OSTI ID:
- 22975258
- Report Number(s):
- INIS-US-20-WM-18031; TRN: US21V0072015300
- Resource Relation:
- Conference: WM2018: 44. Annual Waste Management Conference, Phoenix, AZ (United States), 18-22 Mar 2018; Other Information: Country of input: France; 4 refs.; Available online at: https://www.xcdsystem.com/wmsym/2018/index.html
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BN-350 REACTOR
CEMENTS
CESIUM 137
DECOMMISSIONING
ENCAPSULATION
KAZAKHSTAN
LIQUID WASTES
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTE STORAGE
REACTOR SITES
SOLIDIFICATION
STRONTIUM 90
SULFUR
TBP
URANIUM 235
WASTE FORMS
WASTE OILS