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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
F. T. Cross, J. C. Sheppard
Nuclear Technology | Volume 13 | Number 1 | January 1972 | Pages 83-94
Technical Paper | Radioisotope | doi.org/10.13182/NT72-A31070
Articles are hosted by Taylor and Francis Online.
The dose rates from an implanted 238Pu heat source have been measured and calculated. The source material was medical grade plutonium of nominal 30-W strength. The tissue-equivalent phantoms were both a large homogeneous right-circular cylinder and a man-simulating Remab phantom. Calculated dose rates agreed to within 20% with measured values except for positions very close to the source. The reasons for discrepancies greater than this are thought mainly to arise from the uncertainties in the photon emission rate and the use of dosimeters too large for neutron measurements close to the source. In general, the agreement of the measured and calculated values is good, at least in the regions where the photons and neutrons make their greatest dose contribution for a source enclosed in a circulatory support system. It is concluded that an artificial heart device incorporating a medical grade plutonium heat source is probably acceptable to the recipient from a radiation dose standpoint independent of its acceptability as a prosthetic device.