ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Jun 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
August 2026
Nuclear Technology
July 2026
Fusion Science and Technology
Latest News
Launching into tomorrow: NRIC guides new era of research and deployment
In June 2025, the Department of Energy announced the Reactor Pilot Program, an authorization pathway that allowed reactor developers to partner with the DOE to get first-of-a-kind (FOAK) reactors built and tested. Soon after, the DOE rolled out a complementary Fuel Line Pilot Program, which aimed to fast-track fuel projects. In all, 20 projects were accepted into the new programs.
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.