scholarly journals Low-Activity Waste and High-Level Waste Feed Processing Data Quality Objectives

10.2172/5856 ◽  
1999 ◽  
Author(s):  
GK Patello ◽  
MJ Truex ◽  
KD Wiemers
Keyword(s):  
Data Quality ◽  
High Level Waste ◽  
Feed Processing ◽  
Processing Data ◽  
High Level ◽  
Low Activity

scholarly journals Low-Activity Waste and High-Level Waste Feed Processing Data Quality Objectives

1999 ◽  
Author(s):  
Gertrude K. Patello ◽  
Michael J. Truex ◽  
Karyn D. Wiemers
Keyword(s):  
Data Quality ◽  
High Level Waste ◽  
Feed Processing ◽  
Processing Data ◽  
High Level ◽  
Low Activity

Lessons Learned Siting and Successfully Processing U.S. DOE Radioactive Wastes Using a High Throughput Vitrification Process

2003 ◽  
Author(s):  
Robert E. Prince ◽  
Bradley W. Bowan
Keyword(s):  
The United States ◽  
Lessons Learned ◽  
Volume Reduction ◽  
Waste Form ◽  
High Level Waste ◽  
Hanford Site ◽  
High Level ◽  
Low Activity ◽  
The U.S ◽  
Ceramic Melter

This paper describes actual experience applying a technology to achieve volume reduction while producing a stable waste form for low and intermediate level liquid (L/ILW) wastes, and the L/ILW fraction produced from pre-processing of high level wastes. The chief process addressed will be vitrification. The joule-heated ceramic melter vitrification process has been used successfully on a number of waste streams produced by the U.S. Department of Energy (DOE). This paper will address lessons learned in achieving dramatic improvements in process throughput, based on actual pilot and full-scale waste processing experience. Since 1991, Duratek, Inc., and its long-term research partner, the Vitreous State Laboratory of The Catholic University of America, have worked to continuously improve joule heated ceramic melter vitrification technology in support of waste stabilization and disposition in the United States. From 1993 to 1998, under contact to the DOE, the team designed, built, and operated a joule-heated melter (the DuraMelterTM) to process liquid mixed (hazardous/low activity) waste material at the Savannah River Site (SRS) in South Carolina. This melter produced 1,000,000 kilograms of vitrified waste, achieving a volume reduction of approximately 70 percent and ultimately producing a waste form that the U.S. Environmental Protection Agency (EPA) delisted for its hazardous classification. The team built upon its SRS M Area experience to produce state-of-the-art melter technology that will be used at the DOE’s Hanford site in Richland, Washington. Since 1998, the DuraMelterTM has been the reference vitrification technology for processing both the high level waste (HLW) and low activity waste (LAW) fractions of liquid HLW waste from the U.S. DOE’s Hanford site. Process innovations have doubled the throughput and enhanced the ability to handle problem constituents in LAW. This paper provides lessons learned from the operation and testing of two facilities that provide the technology for a vitrification system that will be used in the stabilization of the low level fraction of Hanford’s high level tank wastes.

scholarly journals Melter feed viscosity during conversion to glass: Comparison between low‐activity waste and high‐level waste feeds

2017 ◽  
Vol 101 (5) ◽  
pp. 1880-1891 ◽  
Author(s):  
Tongan Jin ◽  
Jaehun Chun ◽  
Derek R. Dixon ◽  
Dongsang Kim ◽  
Jarrod V. Crum ◽  
...  
Keyword(s):  
High Level Waste ◽  
High Level ◽  
Low Activity

scholarly journals High-Level Waste Feed Data Quality Objectives

1998 ◽  
Author(s):  
Karyn D. Wiemers ◽  
Michael C. Miller ◽  
Gertrude K. Patello
Keyword(s):  
Data Quality ◽  
High Level Waste ◽  
High Level

Free Release of Radioactive Waste Containing Very Low Level Waste and Short Lived Radionuclides at Nucleco

2018 ◽  
Author(s):  
C. Andreozzi ◽  
B. Bianchilli ◽  
A. Dodaro ◽  
F. Gagliardi ◽  
E. Mauro ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Electricity Production ◽  
High Level Waste ◽  
Reference Spectrum ◽  
New Classification ◽  
Final Destination ◽  
Activity Concentrations ◽  
High Level ◽  
Sampling Procedures ◽  
Low Activity

Since August 2015 a new classification of radioactive waste was issued by Italian Ministry of Economic Development, in order to adapt Italian historical classification to European standards. This new classification provides 6 categories, from exempt to high level waste, and it is based on the waste final destination: from free release to final disposal or interim storage (high level waste and intermediate level waste with α-content higher than 400 Bq/g) [1]. Nucleco is a State owned Company acting as Waste Management Organization for radioactive waste coming from hospitals, industries and research and development activities not related to electricity production by nuclear plants. Nucleco collects, safely manages and temporarily stores waste that will be sent to the National Repository (site definition phase is still ongoing), while for the Short Lived Radionuclides and Very Low Activity waste Nucleco performs all necessary operations to be compliant with the conditions of release prescribed by the Italian Control Authority. Short Lived Radionuclides are those whose half-life is shorter than 100 days or reach the condition of non-radiological relevance in 5 years: they are mainly produced by bio-medical applications of radioactive materials. Very Low Activity waste are characterized by activity concentrations lower than 100 Bq/g (of which less than 10 Bq/g of α-emitting radionuclides) and reach the condition of non-radiological relevance in 10 years: these waste usually came from research institutions and industrial activities. This work presents the authorized operating procedures, the radiological measurements criteria and the technical know-how put in place by Nucleco to fulfil the provisions of Italian regulations for unconditioned release of radioactive waste. A case study of ISO 20’ containers is discussed in the current paper. Main emphasis will be addressed to: • gathering of historical information about the state of the material to be released and definition of the reference radiological spectrum; • sampling procedures to ensure representativeness of the samples from homogeneous waste batch to be released and then subjected to radiological characterization; • characterization phase consisting of the integration of several state-of-art techniques aiming to collect the most complete set of radiological data; • data processing protocols needed for the calculation of the activity concentrations for each radionuclide of the reference spectrum (or other radionuclides eventually detected); • evaluation of the main sources of uncertainty affecting the results; • comparison of the activity concentration (including the uncertainty) of each radionuclide with the corresponding authorized concentration limits.

scholarly journals Waste Loading Enhancements for Hanford Low-Activity Waste Glasses

2011 ◽  
Author(s):  
Albert A. Kruger
Keyword(s):  
Waste Treatment ◽  
The United States ◽  
Washington State ◽  
High Level Waste ◽  
United States Department ◽  
Hanford Site ◽  
Geological Repository ◽  
High Level ◽  
Low Activity ◽  
Tank Waste

About 50 million gallons of mixed waste is currently stored in underground tanks at The United States Department of Energy’s (DOE) Hanford site in Washington state. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) will provide the Office of River Protection (ORP) with a means of treating this waste by vitrification for subsequent disposal. The tank waste will be separated into low- and high-activity waste fractions, which will then be vitrified respectively into Immobilized Low Activity Waste (ILAW) and Immobilized High Level Waste (IHLW) products. The ILAW product is destined for disposal in an engineered facility at Hanford site while the IHLW product will be disposed in a national geological repository. Both waste forms must meet a variety of requirements to ensure the protection of the environment before they can be accepted for disposal.

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