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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Taira Hazama, Akihiro Kitano, Y. Kishimoto
Nuclear Technology | Volume 179 | Number 2 | August 2012 | Pages 250-265
Technical Paper | Fission Reactors | doi.org/10.13182/NT12-A14097
Articles are hosted by Taylor and Francis Online.
The Japanese prototype fast breeder reactor Monju restarted its system startup test in May 2010 after a 14-year interruption. In the first stage of the test, reactor physics parameters have been measured at a zero power level.The present paper describes the evaluation of the criticality data. The best-estimate value and its uncertainty are evaluated as accurately as possible, following the guidelines recommended by the International Criticality Safety Benchmark Evaluation Project.The restart core contains 1.5 wt% of 241Am, which is three times more than the previous test. To extract the influence of the 241Am accumulation on calculation accuracy, criticality data obtained in the previous test are evaluated at the same level of detail.The calculation accuracy is investigated with four major nuclear data libraries. It is confirmed that the accuracy is within 0.3% k/k, a 2 value of experimental uncertainty, with JENDL-3.3, JENDL-4.0, and ENDF/B-VII.0. The reactivity change due to the 241Pu decay can be simulated within an accuracy of 1% with JENDL-4.0 and JEFF-3.1.