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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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Nuclear new build procurement considerations
It may seem counterintuitive, but the best time to enhance the ability to support operations and maintenance for a new plant is before construction starts. This is one of many lessons learned by the currently operating nuclear fleet. As construction and startup of many nuclear facilities was completed, it quickly became evident that the ability to efficiently support operations and maintenance was limited. Most of the information necessary to establish and manage procurement of spare and replacement items, maintenance, and configuration of the facilities was unavailable and had to be gathered on a case-by-case, “on-demand” basis. Absence of necessary information and the associated challenges resulted in the need for staff augmentation and multiyear-long projects to develop equipment bills of material and maintenance programs and to perform technical evaluations for the huge quantities of spare and replacement items being requested.
Alessandro Del Novo, Emanuela Martelli
Nuclear Technology | Volume 193 | Number 1 | January 2016 | Pages 1-14
Technical Paper | Special Issue on the RELAP5-3D Computer Code | doi.org/10.13182/NT14-152
Articles are hosted by Taylor and Francis Online.
The International Atomic Energy Agency established a Coordinated Research Project (CRP) for EBR-II shutdown heat removal tests (SHRT). The CRP aims at improving the design and the simulation capabilities in fast reactor neutronics, thermal hydraulics, plant dynamics, and safety analyses. This is achieved by benchmark analyses of protected (SHRT-17) and unprotected (SHRT-45r) loss-of-flow tests, from the EBR-II SHRT program. In this framework, ENEA has set up, applied, and is validating an integrated multiphysics approach, based on existing codes, for supporting the design and the safety analysis of Generation IV liquid-metal fast reactors. This paper outlines the rationale of the CRP participation, and it focuses on the qualification of a three-dimensional (3-D) thermal-hydraulic nodalization of EBR-II and on the assessment of RELAP5-3D code against the test SHRT-17. The nodalization models one by one the fuel assemblies of the core and of the extended core of the reactor for an efficient coupling with a 3-D neutron kinetic analysis code. The experimental data are presented and the thermal-hydraulic phenomena of test SHRT-17 are discussed, being the basis for assessing the code performance and for discussing its limitations. Blind and open calculation results are presented and discussed.