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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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Fusion Science and Technology
Latest News
DOE issues RFI for a spent fuel consolidated interim storage facility
The Department of Energy’s Office of Nuclear Energy has issued a request for information opportunity for the design and construction of a federal consolidated interim storage facility (CISF) for spent nuclear fuel. The DOE is planning on establishing a federal CISF to manage SNF until a permanent repository is available. In May, the DOE received initial approval, known as “Critical Decision-0,” for such a facility.
The deadline for submissions is September 5.
Yasufumi Tanaka, Heun Tae Lee, Yoshio Ueda, Masayoshi Nagata, Yusuke Kikuchi, Satoshi Suzuki, Yohji Seki
Fusion Science and Technology | Volume 68 | Number 2 | September 2015 | Pages 433-437
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST15-109
Articles are hosted by Taylor and Francis Online.
In this study, surface damaged W monoblocks (melting and cracking) by a pulsed plasma gun and an e-beam devices were exposed to cyclic heat loads (simulating normal heat loads and slow transients) and pulsed heat loads (simulating ELMs) to observe the effects of surface damage on surface erosion and heat removal capability. Heat load tests simulating the normal heat load (10 MW/m2, 10 sec, 300 cycles) and the slow transient (~20 MW/m2, 10 sec, 300 cycles) were performed by the e-beam. The surface morphology changes after the heat load tests were observed using laser scanning microscopy and FE-SEM. After e-beam irradiation of ~20 MW/m2, the longitudinal cracks crossing over entire monoblocks appeared on the surfaces of all monoblocks. Recrystallization and additional crack formation were also observed on the surface. However, there was no significant change of heat removal capability. In the additional pulsed heat load test, the energy fluence of 0.042-0.30MJ/m2 was applied with pulse numbers of 103 and 104.The surface morphology changes after laser irradiation were observed using laser scanning microscope. After laser irradiation, the grain ejection occurred above a certain energy fluence (~25 % of melting threshold).