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 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Apr 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
May 2026
Nuclear Technology
March 2026
Fusion Science and Technology
Latest News
In quickest review, NRC approves 20-year renewal for Robinson
The Nuclear Regulatory Commission has renewed the Robinson nuclear power plant’s operating license in record time, the agency announced last week.
The subsequent license renewal process for the Hartsville, S.C., facility was completed within 12 months, according to the NRC. The process has typically taken 18 months. This was the first license renewal review conducted under the directive of Executive Order 14300 to streamline processes like renewing operating licenses.
Xuegao An, Vijay K. Dhir, David Okrent
Nuclear Technology | Volume 132 | Number 2 | November 2000 | Pages 256-280
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3143
Articles are hosted by Taylor and Francis Online.
The damage progression of the reactor core and the slumping mechanism of molten material to the lower head of the reactor vessel were examined through simulation of severe accident scenarios that lead to large-scale core damage. The calculations were carried out on a Three Mile Island Unit 2 configuration using the computer code SCDAP/RELAP5/MOD3.2.Different accident scenarios were simulated. The high-pressure injection and makeup flow rates were changed. The extreme case with no water being added during the accident was examined. Reflood by restart of coolant pump 2B was also studied. Finally, the size of the power-operated relief valve opening was also changed. The effects of these accident scenarios on the accident progression and the core damage process were studied.It is concluded that, according to code MOD3.2, the molten material slumped to the lower head of the reactor vessel when the junction of the top and side crusts failed after the molten pool had reached the periphery of the core. When the effective stress caused by pressure imbalance inside and outside of the crust became larger than the ultimate strength of the crust, the crust failed mechanically.