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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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Latest News
NRC issues subsequent license renewal to Monticello plant
The Nuclear Regulatory Commission has renewed for a second time the operating license for Unit 1 of Minnesota’s Monticello nuclear power plant.
Hidehito Kinjo, Takeshi Kageyama, Akihiro Kitano, Shin Usami
Nuclear Technology | Volume 167 | Number 2 | August 2009 | Pages 254-267
Technical Paper | Fission Reactors | doi.org/10.13182/NT09-A8962
Articles are hosted by Taylor and Francis Online.
A conceptual design study has been performed on upgrading the core performance of the Japanese fast breeder reactor (FBR) Monju. The main aim of this study is to investigate and demonstrate the feasibility of an upgraded core with an extended refueling interval of 365 equivalent full-power days and increased average fuel burnup of 150 GWd/t, which are expected in future commercial FBRs.Two main design measures have been taken to accommodate the largely increased burnup reactivity loss and the reactivity control characteristics for the 1-yr cycle operation: (a) A modified fuel pin specification with increased pin diameter, pellet density, and fissile height has been chosen to improve the burnup reactivity loss per extended cycle, and (b) the control rod specification has been modified to enhance the reactivity worth by increasing the 10B content to ensure sufficient shutdown margin.The major core characteristics that have been evaluated are the core power distribution, safety-related reactivities such as Doppler and sodium void effect, thermal hydraulics, and reactivity control characteristics. The results show that even a medium-sized upgraded core with a volume of [approximately]2.5 m3 could achieve the primary targeted performance of 1-yr cycle operation, without causing significant drawbacks to the core characteristics and safety aspects. The feasibility of the upgraded core concept has thus been demonstrated.