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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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New coolants, new fuels: A new generation of university reactors
Here’s an easy way to make aging U.S. power reactors look relatively youthful: Compare them (average age: 43) with the nation’s university research reactors. The 25 operating today have been licensed for an average of about 58 years.
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.