Published 1997 | Version v1
Journal article

Characterization of aerosols from industrial fabrication of mixed-oxide nuclear reactor fuels

  • 1. Lovelace Respiratory Research Institute, Albuquerque, NM (United States)

Description

Recycling plutonium into mixed-oxide (MOX) fuel for nuclear reactors is being given serious consideration as a safe and environmentally sound method of managing plutonium from weapons programs. Planning for the proper design and safe operation of the MOX fuel fabrication facilities can take advantage of studies done in the 1970s, when recycling of plutonium from nuclear fuel was under serious consideration. At that time, it was recognized that the recycle of plutonium and uranium in irradiated fuel could provide a significant energy source and that the use of 239Pu in light water reactor fuel would reduce the requirements for enriched 235U as a reactor fuel. It was also recognized that the fabrication of uranium and plutonium reactor fuels would not be risk-free. Despite engineered safety precautions such as the handling of uranium and plutonium in glove-box enclosures, accidental releases of radioactive aerosols from normal containment might occur. Workers might then be exposed to the released materials by inhalation

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
77
Journal Page Range
p. 155-156.
ISSN
0003-018X
CODEN
TANSAO

Conference

Title
1997 American Nuclear Society (ANS) winter meeting.
Dates
16-20 Nov 1997.
Place
Albuquerque, NM (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
29020970
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FABRICATION; INHALATION; MIXED OXIDE FUELS; OCCUPATIONAL EXPOSURE; PLUTONIUM; RADIOACTIVE AEROSOLS; SOURCE TERMS; URANIUM
Descriptors DEC
ACTINIDES; AEROSOLS; COLLOIDS; DISPERSIONS; ELEMENTS; ENERGY SOURCES; FUELS; INTAKE; MATERIALS; METALS; NUCLEAR FUELS; REACTOR MATERIALS; SOLID FUELS; SOLS; TRANSURANIUM ELEMENTS

Optional Information

Secondary number(s)
CONF-971125--.