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.
Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Jul 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
Ralph W. Seidensticker, Algirdas H. Marchertas, Zdeněk P. Bažant
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 443-451
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32580
Articles are hosted by Taylor and Francis Online.
The Argonne National Laboratory developed computer program DYNAPCON for the transient analysis of a prestressed concrete reactor vessel (PCRV) for liquid-metal fast breeder reactor (LMFBR) primary containment is applied to a reference design concept representative of large, pool-type LMFBR reactor plants. Estimates of the energy absorption capability of a PCRV primary containment vessel are provided to assist in the establishment of the engineering feasibility of such a design concept. The reference design analyzed utilizes existing concrete structures already in place for biological shielding and component support. The very large energy absorption capability is achieved through the use of fairly large amounts of prestressing steel and mild steel reinforcement within these concrete matrices. Energy sources used range from 2720 to 10 880 MW-s. Even for the largest energy source, the maximum computed strain in the prestressing tendon anywhere in the structure is ∼2.3%, which is still below the strain associated with the minimum ultimate stress levels for most prestressing steels. These results are very encouraging and should provide sufficient incentive to more firmly establish the feasibility of this concept of using a PCRV for primary containment.