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