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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
Stanley Rosen, Richard D. Ivany, John F. Kapinos, Suk K. Sim
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 89-94
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Safety | doi.org/10.13182/NT90-A34444
Articles are hosted by Taylor and Francis Online.
Combustion Engineering’s advanced light water reactor, System 80+, is an evolutionary upgrade of the proven System 80® nuclear steam supply system design. While both plants are rated at 3817 MW(thermal), System 80+ incorporates a number of design enhancements, including direct vessel injection for the safety injection (SI) system and other changes to the reactor cooling system. The results of a best-estimate small-break loss-of-coolant accident (LOCA) study that addresses utility investment protection concerns is presented. Specifically, the size piping break that can be tolerated without the liquid or two-phase fluid level falling below the top of the active core is addressed. Using best-estimate analytical procedures, and assuming no single failure, the active core remains covered with substantial margin for breaks up to 0.254-m (10-in.) diameter. This reduces the possibility of core damage due to a small LOCA. A large-break, cold-leg LOCA licensing analysis is also presented that addresses the reflood capability after the end of SI tank discharge without credit for a low-pressure SI pump system. This analysis confirms that the improved high-pressure SI system provides adequate reflood capability to satisfy the U.S. Nuclear Regulatory Commission LOCA licensing criteria.