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Title: Concentration of HLLW from Future SNF Recycling for Efficient Immobilization in a CCIM

Abstract

Sponsored by the Department of Energy Nuclear Energy’s Fuel Cycle Research and Development Program, the Cold Crucible Induction Melter is being developed as the next generation of melter technology for High Level Liquid Waste’s efficient immobilization in highly durable glass ceramic and ceramic forms. Concentration of the radioactive High Level Liquid Waste generated from the proposed future recycling of spent nuclear fuel, after the fuel’s dissolution in nitric acid, is necessary to take advantage of the inherent attributes of Cold Crucible Induction Melting technology. Based on a provided range of commercial spent nuclear fuel fission product composition data and its expected High Level Liquid Waste raffinate composition data as provided in oxide form, an analysis was completed to concentrate the waste. The analysis involved using nitric acid vapor liquid equilibrium data over a range of boiling temperatures and performing spreadsheet calculations to concentrate the High Level Liquid Waste through evaporation. The calculation results will provide a concentrated nonradioactive surrogate High Level Liquid Waste melter feed recipe for testing in Idaho National Laboratory’s Cold Crucible Induction Melter Pilot Plant. This testing will provide a quantifiable verification of the relatively high feed rates of Cold Crucible Induction Melters compared to those achievablemore » with the current ceramic lined Joule Heated Melters.« less

Authors:
 [1];  [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1173090
Report Number(s):
INL/EXT-13-28484
TRN: US1500069
DOE Contract Number:
AC07-05ID14517
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 12 MGMT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; HIGH-LEVEL RADIOACTIVE WASTES; Liquid Wastes; SPENT FUELS; EVAPORATION; Vitrification; Ceramic Melters; Radioactive Waste Processing; RECYCLING; CRUCIBLES; INDUCTION; PILOT PLANTS; COMPARATIVE EVALUATIONS; TESTING; VERIFICATION; Aqueous Based Used Nuclear Fuel Recycling; Concentration Calculations; Evaporation; High Level Liquid Waste

Citation Formats

Maio, Vince, and Rutledge, Roni. Concentration of HLLW from Future SNF Recycling for Efficient Immobilization in a CCIM. United States: N. p., 2015. Web. doi:10.2172/1173090.
Maio, Vince, & Rutledge, Roni. Concentration of HLLW from Future SNF Recycling for Efficient Immobilization in a CCIM. United States. doi:10.2172/1173090.
Maio, Vince, and Rutledge, Roni. Thu . "Concentration of HLLW from Future SNF Recycling for Efficient Immobilization in a CCIM". United States. doi:10.2172/1173090. https://www.osti.gov/servlets/purl/1173090.
@article{osti_1173090,
title = {Concentration of HLLW from Future SNF Recycling for Efficient Immobilization in a CCIM},
author = {Maio, Vince and Rutledge, Roni},
abstractNote = {Sponsored by the Department of Energy Nuclear Energy’s Fuel Cycle Research and Development Program, the Cold Crucible Induction Melter is being developed as the next generation of melter technology for High Level Liquid Waste’s efficient immobilization in highly durable glass ceramic and ceramic forms. Concentration of the radioactive High Level Liquid Waste generated from the proposed future recycling of spent nuclear fuel, after the fuel’s dissolution in nitric acid, is necessary to take advantage of the inherent attributes of Cold Crucible Induction Melting technology. Based on a provided range of commercial spent nuclear fuel fission product composition data and its expected High Level Liquid Waste raffinate composition data as provided in oxide form, an analysis was completed to concentrate the waste. The analysis involved using nitric acid vapor liquid equilibrium data over a range of boiling temperatures and performing spreadsheet calculations to concentrate the High Level Liquid Waste through evaporation. The calculation results will provide a concentrated nonradioactive surrogate High Level Liquid Waste melter feed recipe for testing in Idaho National Laboratory’s Cold Crucible Induction Melter Pilot Plant. This testing will provide a quantifiable verification of the relatively high feed rates of Cold Crucible Induction Melters compared to those achievable with the current ceramic lined Joule Heated Melters.},
doi = {10.2172/1173090},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Jan 01 00:00:00 EST 2015},
month = {Thu Jan 01 00:00:00 EST 2015}
}

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