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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
K. Hnilica, H. P. Holley, K. Lahner, H. Schmale
Nuclear Technology | Volume 31 | Number 1 | October 1976 | Pages 53-61
Technical Paper | Fuel Cycle | doi.org/10.13182/NT76-A31698
Articles are hosted by Taylor and Francis Online.
The economic incentives for utilizing the plutonium produced in light water reactors can be evaluated for two alternatives: stockpiling or successive recycling of the self-generated plutonium obtained from 1200-MW(e) pressurized water reactor (PWR) and boiling water reactor (BWR) power stations. The economic analysis covers an operating period of 20 yr, starting in 1976. The recycling of plutonium begins with the fourth fuel cycle, and the reload fuel batches consist then of uranium fuel elements and U/Pu fuel elements of the all-rod design in appropriate number to use all the self-generated plutonium of the reprocessed fuel elements from previous cycles. The necessary nuclear data for the fuel cycle cost calculations were obtained by detailed physics calculations. The economic analysis is based on 1976 cost data on different fabrication penalties for the U/Pu assemblies and a plutonium market price of zero. This last assumption is justified for utilities by the lack of a functioning plutonium market and is used as the basis to determine a realistic valuation of plutonium. The obtained levelized fuel costs are discussed in detail for the PWR with and without successive plutonium recycling. Results for the BWR are discussed for comparison purposes. The comparison of fuel cycle cost for the two cases with and without plutonium recycling shows for a plutonium market price of zero and a fabrication penalty of 100% for U/Pu fuel elements a cumulative cost saving of 7% in the case of recycling plutonium in the PWR after 20 yr of operation. Similarly, 6% are obtained for the BWR. Any additional increase in the fabrication penalty by 100% reduces the savings by 1.2%, whereas the influence of the diluent material is practically negligible. If the storage charges for the bred plutonium are taken into consideration, the cost reductions increase further. For low plutonium sale prices, a limited storage period can be economically attractive for a utility, especially if at a later date a higher plutonium sale price is obtainable. Therefore, in the present analysis the minimum plutonium sale price that has to be obtained for the stored plutonium at the selling date was determined by using the following balance equation: For simplicity, the plutonium price was set to zero during the storage period and has a value only at the selling date. To determine an economically justified storage period, the obtained plutonium sale prices are compared to the price of 1 g of 93% enriched uranium. The results of the present analysis indicate for a fabrication penalty of 100% for U/Pu fuel assemblies and a yearly storage charge of 2 $/g Putot, storage time is ∼10 yr for the BWR and PWR. Furthermore, the economically acceptable storage periods increase with increasing fabrication penalties. If, in addition, the removal charges for americium (if the plutonium is stored in form of PuO2) are included, the storage periods are ∼2 yr shorter.
