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
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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!
Latest Magazine Issues
Sep 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
October 2025
Nuclear Technology
September 2025
Fusion Science and Technology
Latest News
NNSA awards BWXT $1.5B defense fuels contract
The Department of Energy’s National Nuclear Security Administration has awarded BWX Technologies a contract valued at $1.5 billion to build a Domestic Uranium Enrichment Centrifuge Experiment (DUECE) pilot plant in Tennessee in support of the administration’s efforts to build out a domestic supply of unobligated enriched uranium for defense-related nuclear fuel.
W. S. Yeung, J. Shirkov, F. Seifaee
Nuclear Technology | Volume 108 | Number 3 | December 1994 | Pages 387-394
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A35021
Articles are hosted by Taylor and Francis Online.
The capability of the RELAP5/MOD3 computer code to analyze water hammer transients due to water column rejoining and a water slug propelled by non-condensable gas is investigated. The code-calculated results have been compared with those obtained from simple ideal analytical models. Good agreement is obtained between the calculation and analytical results in the initial period of the transient during which the water column or slug retains its sharp interface and suffers from little breakup or dissipation. As the transient proceeds, the code-calculated hydrodynamic loads are generally less than those implied by the analytical models. This is most likely due to the breakup of the water phase, which is not taken into account in the analytical models. Effects of time step and mesh sizes have also been studied. The results show that the usual Courant time limit applies. Finally, a sample calculation, corresponding to a water hammer transient in a typical Westinghouse four-loop reactor head vent system piping, is presented. The transient is induced by the opening of a relief valve and accelerating a trapped water slug through the pipeline. Hydrodynamic loads (i.e., force-time curves) on various pipe segments have been evaluated by appropriate postprocessing of the transient results. The calculated peak forces at selected pipe segments compare favorably with those estimated from the analytical models.