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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
Yoshihiro Nakane, Teruo Abe, Hiroshi Nakashima
Nuclear Technology | Volume 168 | Number 2 | November 2009 | Pages 519-523
Shielding | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 2) / Accelerators | doi.org/10.13182/NT09-A9236
Articles are hosted by Taylor and Francis Online.
Radiation shielding calculations were performed for the shielding design around beam injection and beam extraction areas at the 3-GeV proton synchrotron in the Japan Proton Accelerator Research Complex (J-PARC) with the PHITS Monte Carlo code. Prompt dose rates outside the shields were obtained from calculated neutron energy spectra and flux-to-dose conversion coefficients prepared for the shielding design in J-PARC. The thicknesses of shields were determined from the comparison results of the prompt dose rates with the criteria of dose limit for the design in J-PARC.
