Release of neptunium, plutonium, uranium and technetium from the metallic waste form from the electrometallurgical treatment process

S. G. Johnson; M. Noy; T. DiSanto; T. L. Barber

doi:10.1557/proc-713-jj11.73

Release of neptunium, plutonium, uranium and technetium from the metallic waste form from the electrometallurgical treatment process

S. G. Johnson
, M. Noy
, T. DiSanto
, T. L. Barber

Materials and Fuels Complex

Research output: Contribution to journal › Conference article › peer-review

4 Scopus citations

Abstract

This waste form is an alloy consisting of stainless steel with 15 wt% zirconium and acts as a host for the immobilization of radioelements that remain with the spent fuel cladding hulls following their treatment using an electrometallurgical treatment process. The results presented here are from 14, 34 and 90-day immersion tests conducted at 90°C. These tests show that the release of uranium is considerably higher than that of all other major elements present (Fe, Cr, Ni, Zr), but that release of all constituents is comparable to or lower than that for borosilicate glass.

Original language	English
Pages (from-to)	705-712
Number of pages	8
Journal	Materials Research Society Symposium - Proceedings
Volume	713
DOIs	https://doi.org/10.1557/proc-713-jj11.73
State	Published - 2002
Event	Scientific Basis for Nuclear Waste Management XXV - Boston, MA, United States Duration: Nov 26 2001 → Nov 29 2001

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title = "Release of neptunium, plutonium, uranium and technetium from the metallic waste form from the electrometallurgical treatment process",

abstract = "This waste form is an alloy consisting of stainless steel with 15 wt\% zirconium and acts as a host for the immobilization of radioelements that remain with the spent fuel cladding hulls following their treatment using an electrometallurgical treatment process. The results presented here are from 14, 34 and 90-day immersion tests conducted at 90°C. These tests show that the release of uranium is considerably higher than that of all other major elements present (Fe, Cr, Ni, Zr), but that release of all constituents is comparable to or lower than that for borosilicate glass.",

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year = "2002",

doi = "10.1557/proc-713-jj11.73",

language = "English",

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pages = "705--712",

journal = "Materials Research Society Symposium - Proceedings",

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note = "Scientific Basis for Nuclear Waste Management XXV ; Conference date: 26-11-2001 Through 29-11-2001",

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TY - JOUR

T1 - Release of neptunium, plutonium, uranium and technetium from the metallic waste form from the electrometallurgical treatment process

AU - Johnson, S. G.

AU - Noy, M.

AU - DiSanto, T.

AU - Barber, T. L.

PY - 2002

Y1 - 2002

N2 - This waste form is an alloy consisting of stainless steel with 15 wt% zirconium and acts as a host for the immobilization of radioelements that remain with the spent fuel cladding hulls following their treatment using an electrometallurgical treatment process. The results presented here are from 14, 34 and 90-day immersion tests conducted at 90°C. These tests show that the release of uranium is considerably higher than that of all other major elements present (Fe, Cr, Ni, Zr), but that release of all constituents is comparable to or lower than that for borosilicate glass.

AB - This waste form is an alloy consisting of stainless steel with 15 wt% zirconium and acts as a host for the immobilization of radioelements that remain with the spent fuel cladding hulls following their treatment using an electrometallurgical treatment process. The results presented here are from 14, 34 and 90-day immersion tests conducted at 90°C. These tests show that the release of uranium is considerably higher than that of all other major elements present (Fe, Cr, Ni, Zr), but that release of all constituents is comparable to or lower than that for borosilicate glass.

UR - https://www.scopus.com/pages/publications/0036378872

U2 - 10.1557/proc-713-jj11.73

DO - 10.1557/proc-713-jj11.73

M3 - Conference article

AN - SCOPUS:0036378872

SN - 0272-9172

VL - 713

SP - 705

EP - 712

JO - Materials Research Society Symposium - Proceedings

JF - Materials Research Society Symposium - Proceedings

T2 - Scientific Basis for Nuclear Waste Management XXV

Y2 - 26 November 2001 through 29 November 2001

ER -

Release of neptunium, plutonium, uranium and technetium from the metallic waste form from the electrometallurgical treatment process

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