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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Proof of concept: The Molten Salt Reactor Experiment in Nuclear News
By late 1960, when the U.S. Atomic Energy Commission authorized plans to build a Molten Salt Reactor Experiment (MSRE) at Oak Ridge National Laboratory, the lab already had about 13 years of experimentation with molten salt reactors under its longest-serving lab director, Alvin Weinberg. The MSRE operated from 1965 to 1969, proving that molten salt reactors could operate reliably, and with alternatives to uranium-235 too.
Sümer Şahın
Nuclear Technology | Volume 92 | Number 1 | October 1990 | Pages 93-105
Technical Paper | Development of Nuclear Gas Cleaning and Filtering Techniques / Fission Reactor | doi.org/10.13182/NT90-A34489
Articles are hosted by Taylor and Francis Online.
A straightforward numerical-graphical method is applied to achieve a flat fission power density (FPD) in a catalyzed deuterium-deuterium fusion-driven hybrid blanket by using a mixed fuel made of a nuclear waste actinide (244CmCO2) and natural UO2 with variable fractions of fuel components in the radial direction. The FPD could be kept quasi-constant over a relatively long plant lifetime. The peak-to-average FPD increases from 1.071 at start-up to ∼ 1.074 after 18 months’ operation. The plant availability factor is 60% under a first-wall fusion neutron flux load of 1014 x 2.45- and 1014 x 14.1-MeV neutron/cm2.s, corresponding to ∼2.64 MW/m2. This eliminates the fuel management requirements for at least 18 months of plant operation. The investigated blanket breeds high-quality nuclear fuel (239Pu and 245Cm) and also produces electricity. The overall blanket multiplication factor M increases from 9.4 to only 9.8 in 18 months. This allows an optimal exploitation of the nonnuclear part of the power plant.