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Electrometallurgical Techniques for DOE Spent Fuel Treatment: Final Report (2000)

Chapter: Appendix E Abbreviations and Acronyms

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Suggested Citation:"Appendix E Abbreviations and Acronyms." National Research Council. 2000. Electrometallurgical Techniques for DOE Spent Fuel Treatment: Final Report. Washington, DC: The National Academies Press. doi: 10.17226/9883.
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APPENDIX E
Abbreviations and Acronyms


ACM

anode-cathode module

AES

Auger electron spectroscopy

ALMR/IFR

Advanced Liquid-Metal Reactor/Integral Fast Reactor

ANL

Argonne National Laboratory

ANL-E

Argonne National Laboratory-East (Argonne, Illinois)

ANL-W

Argonne National Laboratory-West (Idaho Falls, Idaho)

ANSTO

Australian Nuclear Science and Technology Organisation

ASTM

American Society for Testing and Materials


CCDF

compliance cumulative distribution functions

CISAC

Committee on International Security and Arms Control

CWF

ceramic waste form


DHLW

Defense Program High-Level Waste

DOE

U.S. Department of Energy

DOE-EM

U.S. Department of Energy’s Office of Environmental Management

DOE-RW

U.S. Department of Energy, Office of Civilian Radioactive Waste Management

DSC

differential scanning calorimetry

DU

depleted uranium

DWPF

Defense Waste Processing Facility


EA

environmental assessment

EBR-II

Experimental Breeder Reactor-II

EBS

engineered barrier system

EIS

environmental impact statement

EMT

electrometallurgical technology


FCF

fuel conditioning facility

FDB

fuel dissolution basket

FFTF

Fast Flux Test Facility


GMODS

glass material oxidation and dissolution


HEU

highly enriched uranium

HFEF

Hot Fuel Examination Facility

Suggested Citation:"Appendix E Abbreviations and Acronyms." National Research Council. 2000. Electrometallurgical Techniques for DOE Spent Fuel Treatment: Final Report. Washington, DC: The National Academies Press. doi: 10.17226/9883.
×

HIP

hot isostatic press

HLW

high-level waste

HTER

high-throughput electrorefiner

HUP

hot uniaxial press


INEEL

Idaho National Engineering and Environmental Laboratory

INTEC

Idaho Nuclear Technology and Engineering Center


J-13

simulated Yucca Mountain well water


LEU

low enriched uranium

LLW

low-level waste

LWR

light water reactor


MCC

Material Characterization Center

MGDSWAC

mined geologic disposal system waste acceptance criteria

MOA

memorandum of agreement

MOX

mixed uranium-plutonium oxide fuel

MSRE

molten salt reactor experiment

MTHM

metric tons heavy metal

MWF

metal waste form


NE

U.S. Department of Energy Office of Nuclear Energy, Science, and Technology


PCT

product consistency test


R&D

research and development

RIP

repository integration program


SEM

scanning electron microscopy

SNF

spent nuclear fuel

SRS

Savannah River site

SS

stainless steel


TCLP

toxicity characteristic leaching procedure

TEM

transmission electron spectroscopy

TRU

transuranic elements

TSPA

total system performance assessment


WAPS

waste acceptance product specifications

WCP

waste form compliance plan

WIPP

waste isolation pilot plant

WISP

Waste Isolation System Panel

WPu

weapons plutonium

WQR

waste form qualification report


XAFS

X-ray absorption fine structure spectroscopy

XPS

X-ray photoelectron spectroscopy

XRD

X-ray diffraction

Suggested Citation:"Appendix E Abbreviations and Acronyms." National Research Council. 2000. Electrometallurgical Techniques for DOE Spent Fuel Treatment: Final Report. Washington, DC: The National Academies Press. doi: 10.17226/9883.
×
Page 115
Suggested Citation:"Appendix E Abbreviations and Acronyms." National Research Council. 2000. Electrometallurgical Techniques for DOE Spent Fuel Treatment: Final Report. Washington, DC: The National Academies Press. doi: 10.17226/9883.
×
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The Committee on Electrometallurgical Techniques for DOE Spent Fuel Treatment was formed in September 1994 in response to a request made to the National Research Council (NRC) by the U.S. Department of Energy DOE. DOE requested an evaluation of electrometallurgical processing technology proposed by Argonne National Laboratory (ANL) for the treatment of DOE spent nuclear fuel. Electrometallurgical treatment of spent reactor fuel involves a set of operations designed to remove the remaining uranium metal and to incorporate the radioactive nuclides into well defined and reproducible waste streams. Over the course of the committee's operating life, this charge has remained constant. Within the framework of this overall charge, the scope of the committee's work—as defined by its statement of task—has evolved in response to further requests from DOE, as well as technical accomplishments and regulatory and legal considerations. As part of its task, the committee has provided periodic assessments of ANL's R&D program on the electrometallurgical technology.

Electrometallurgical Techniques for DOE Spent Fuel Treatment assesses the viability of electrometallurgical technology for treating DOE spent nuclear fuel and monitors the scientific and technical progress of the ANL program on electrometallurgical technology, specifically within the context of ANL's demonstration project on electrometallurgical treatment of EBR-II SNF. This report evaluates ANL's performance relative to the success criteria for the demonstration project, which have served as the basis for judging the efficacy of using electrometallurgical technology for the treatment of EBR-II spent nuclear fuel. It also addresses post-demonstration activities related to ANL's electrometallurgical demonstration project, and makes related recommendations in this area.

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