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Fusion Science and Technology
House Dems introduce clean energy bill for net zero
Democratic leaders in the House last week introduced the Climate Leadership and Environmental Action for our Nation’s Future Act (the CLEAN Future Act, or H.R. 1512), a nearly 1,000-page piece of climate change–focused legislation establishing, among other things, a federal clean electricity standard that targets a 50 percent reduction in greenhouse gas emissions from 2005 levels by 2030 and net-zero emissions by 2050.
The bill, a draft version of which was released in January 2020, presents a sweeping set of policy proposals, both sector-specific and economy-wide, to meet those targets. The final version includes a number of significant revisions to bring the legislation into closer alignment with President Biden’s climate policy campaign pledges. For example, the bill’s clean electricity standard would require all retail electricity suppliers to provide 80 percent clean energy to consumers by 2030 and 100 percent by 2035. (A six-page fact sheet detailing the updates is available online.)
M. Z. Youssef, M. E. Sawan
Fusion Science and Technology | Volume 47 | Number 4 | May 2005 | Pages 1038-1045
Technical Paper | Fusion Energy - First Wall, Blanket, and Shield | dx.doi.org/10.13182/FST05-A824
Articles are hosted by Taylor and Francis Online.
Neutronics testing is among the several types of fusion technology testing scheduled to be performed in ITER. The three ports assigned for testing will test several blanket concepts proposed by the various parties with test blanket modules (TBM) that utilize different breeders and coolants. Nevertheless, neutronics issues to be resolved in ITER-TBM are generic in nature and are important to each TBM type. Dedicated neutronics tests specifically address the accuracy involved in predicting key neutronics parameters such as tritium production rate, TPR, volumetric heating rate, induced activation and decay heat, and radiation damage to the reactor components. In this paper, we address some strategies for performing the neutronics tests. Tritium self-sufficiency cannot be confirmed by testing in ITER, however, the testing can provide valuable information regarding the main parameters needed to assess the feasibility of achieving tritium self-sufficiency. The paper also addresses the operational requirement (i.e. flux and fluence) as well as the geometrical requirement of the test module (i.e. minimum size) in order to have meaningful and useful tests. Measured neutronics data require high spatial resolution. This necessitates that the measured quantity be as flat as possible in the innermost locations inside the test module. This requirement has been confirmed in the present work based on results from two-dimensional calculations. The US and Japan solid breeder test blanket modules are placed inside half a port in ITER. The R- model used accounts for the presence of the ITER shielding blanket and the surrounding frame of the port.