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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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!
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Fabrication milestone for INL’s MARVEL microreactor
A team from Idaho National Laboratory and the Department of Energy’s Office of Nuclear Energy (DOE-NE) recently visited Carolina Fabricators Inc. (CFI), in West Columbia, S.C., to launch the fabrication process for the primary coolant system of the MARVEL microreactor. Battelle Energy Alliance (BEA), which manages INL, awarded the CFI contract in January.
Cornelis H. M. Broeders, Mario Dalle Donne
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 82-95
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33711
Articles are hosted by Taylor and Francis Online.
The work performed at the Karlsruhe Nuclear Center for the neutron physics and thermohydraulic design of an advanced pressurized water reactor is described. Investigations have been restricted to the uranium /plutonium fuel cycle and to light water as coolant/moderator. The idea is to replace the core of a Kraftwerk Union 1300-MW(electric) pressurized water reactor (PWR) with a high-converting core with only minor changes in the internals of the reactor pressure vessel. Two reference designs are presented, a homogeneous one and a heterogeneous (seed and blanket) one, which satisfy the requirement of having a negative reactivity coefficient in case of complete water loss from the core region. With the assumed plutonium vector (PWR discharge and 10-yr ex-core time), the conversion ratios for the homogeneous and the heterogeneous reactor are 0.90 and 0.96, respectively. The net electrical plant output is only marginally lower than that of the PWR (1 to 2%). The target discharge burnup of 50000 MWd/ton can be achieved by increasing the number of fuel element cycles to more than three.