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
Mar 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
March 2026
Nuclear Technology
February 2026
Fusion Science and Technology
April 2026
Latest News
DOE nuclear cleanup costs, schedule delays continue to rise, GAO says
The Department of Energy’s Office of Environmental Management faces significant cost increases, schedule delays, and data management issues in completing nuclear waste cleanup projects, according to a new report from the U.S. Government Accountability Office.
Shunsuke Uchida, Motoaki Utamura, Hideo Yusa, Hideo Maki
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 79-88
Technical Paper | Fuel | doi.org/10.13182/NT78-A26701
Articles are hosted by Taylor and Francis Online.
To improve the efficiency of in-core wet sipping leaker detection, a warm water injection method was developed. The method was characterized by pouring warm water into the channel box through the sipper cap and replacing all the water originally present with the poured water. Basic experiments were performed to determine the efficiency of the method. Mockup experiments were undertaken to confirm this and to ascertain the effects of operational conditions on the efficiency. These were done by the sipping procedures by means of a facility that included a full-scale 8 × 8 simulated fuel assembly. It was demonstrated that (a) the efficiency of detection for bottom leaks increased about a hundred times over the commonly used method, and (b) the increase in efficiency came from flattening the temperature distribution along the axial direction and exciting the natural convection flow in the whole assembly to promote the fission product transfer. Optimal operational conditions for the method were also proposed as follows: