Concentration of Melton Valley Storage Tank surrogates with a wiped film evaporator

Boring,; Farr, L.L.; Fowler, V.L.; Hewitt, J.D.

doi:10.2172/10187377

Cited by 3 publications

(4 citation statements)

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“…C-5.5.4.3 Evaporation and Disengagement Decontamination Factors/Entrainment. The DF for the evaporator was specified as 10,000 based on PEWE performance, and consistent with that determined for most feed components achieved in wiped film evaporator tests conducted at Oak Ridge C-39 (Boring, 1994). Also, discussions with LCI personnel indicated that entrainment for a wiped film evaporator should be essentially zero for the gas flow rates recently tested during SBW trials at LCI (see Griffith, 2003a).…”

Section: C-5542 Extent Of Evaporationmentioning

confidence: 91%

Sodium-bearing Waste Treatment Technology Evaluation Report

Barnes¹,

Olson²,

Taylor³

2004

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A Settlement Agreement between the U.S. Department of Energy (DOE) and the State of Idaho mandates treatment of sodium-bearing waste (SBW) stored at the Idaho Nuclear Technology and Engineering Center located within the Idaho National Engineering and Environmental Laboratory (INEEL). One of the requirements of the Settlement Agreement is to complete treatment of SBW by December 31, 2012. Hence, SBW disposition is one of the Idaho Operation Office's (NE-ID) and State of Idaho's top priorities at the INEEL.The INEEL has been working over the past several years to identify a treatment technology that meets NE-ID and regulatory treatment requirements, including consideration of stakeholder input. Many studies, including the High-Level Waste and Facilities Disposition Environmental Impact Statement, have resulted in the identification of five treatment alternatives that form a short list of perhaps the most appropriate technologies for the DOE to select from. The alternatives are (a) calcination with maximum achievable control technology (MACT) upgrade, (b) steam reforming, (c) cesium ion exchange (CsIX) with immobilization, (d) direct evaporation, and (e) vitrification. Each alternative has undergone some degree of applied technical development and preliminary process design over the past four years.Applied technology development and preliminary process design activities have been required to provide the data necessary for informed decision making and evaluation of the treatment options. A technically defensible selection of a SBW treatment process has been a key driver for the collection of needed data. This document presents a summary of the data gathered in recent years and evaluates the technical maturity of each option by listing and discussing the identified higher-risk technical uncertainties. The SBW issue and the five alternatives are described, and their technical performance (throughputs, waste product descriptions and volumes, preliminary facility footprints, etc.) is summarized in the main body. Details of preliminary process design and applied development activities for three of the alternatives (steam reforming, CsIX with immobilization, and direct evaporation) are presented in three appendices; a recent feasibility study provides the details for calcination. There have been no recent activities performed with regard to vitrification; that section summarizes and references previous work.

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Section: C-5542 Extent Of Evaporationmentioning

confidence: 91%

Sodium-bearing Waste Treatment Technology Evaluation Report

Barnes¹,

Olson²,

Taylor³

2004

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“…A literature review for the performance of MOCs for the transfer lines and the key unit operations for the Recycle Diversion (RD) process under various environments and conditions has indicated that there are at least four principal mechanisms of concern: corrosion [8], [10], erosion [10], [11], erosion-corrosion [12], and fatigue [13], [14]. A brief description of each mechanism is presented in the following sections.…”

Section: Degradation Mechanismsmentioning

confidence: 99%

“…In the 1990s, Oak Ridge National Laboratory (ORNL) needed to process and dispose of transuranic (TRU) waste, which consisted of thick calcium carbonate, aluminum hydroxide, and magnesium hydroxide sludges suspended in solutions that were approximately 4 M sodium nitrate. Pilot-scale tests to concentrate this low-level liquid waste (LLLW) were performed to demonstrate the effectiveness of a WFE unit [10], [57]. The system parameters studied were rotor speed, process fluid feed temperature and feed rate, and evaporator temperature.…”

Section: Wfe Tests At Oak Ridge National Laboratory Supporting Disposition Of Melton Valley Wastementioning

confidence: 99%

“…The mixing tank could be heated with 50 psig steam to 147 ⁰C. In addition to evaluating process variables, the equipment was inspected for corrosion problems and the effects of the waste on the evaporator heat transfer surface due to erosion-corrosion and scaling [10]. The composition of the waste simulant supernate and sludge that were tested are shown in Table 3-11 and Table 3-12, respectively.…”

Section: Wfe Tests At Oak Ridge National Laboratory Supporting Disposition Of Melton Valley Wastementioning

confidence: 99%

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An Assessment of the Materials of Construction for the Transfer Lines and Unit Operations Equipment Associated with the Recycle Diversion Process

Wiersma

2021

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Oak Ridge National Laboratory Melton Valley Storage Tanks Waste filtration process evaluation

Walker¹,

McCabe²

1997

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Concentration of Melton Valley Storage Tank surrogates with a wiped film evaporator

Abstract: Portions of this document may be illegible in electronic image products. Images are produced from the best available original document.

Cited by 3 publications

References 0 publications

Sodium-bearing Waste Treatment Technology Evaluation Report

Sodium-bearing Waste Treatment Technology Evaluation Report

An Assessment of the Materials of Construction for the Transfer Lines and Unit Operations Equipment Associated with the Recycle Diversion Process

Oak Ridge National Laboratory Melton Valley Storage Tanks Waste filtration process evaluation

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