Published December 2018 | Version v1
Book

BISON for Metallic Fuels Modelling

  • 1. Los Alamos National Laboratory, Los Alamos, NM (United States)
  • 2. Idaho National Laboratory, Idaho Falls, ID (United States)

Description

The fuel performance code BISON has recently been extended to simulate U-Zr and U-Pu-Zr metallic fuel rods irradiated in the US sodium cooled fast reactor EBR-II. By introducing fuel and clad specific material models, the backbone provided by the MOOSE/BISON software architecture has allowed rapid development of metallic fuel capabilities. Zirconium based fuels present unique challenges due to the different phases that exist at irradiation temperatures. Each phase possess differing thermo-mechanical properties, necessitating explicit tracking of the relative concentration of phases throughout the fuel rod in order to capture the integral behavior. In addition, the transition locations between phases change over the course of irradiation due to zirconium diffusion in the fuel, necessitating coupling of the thermo-mechanical simulation to the Fickian and Soret diffusion of Zr. Along with a robust U-Zr and U-Pu-Zr zirconium redistribution model, coupling of zirconium concentration to local power deposition allows for several coupled thermo-diffusion simulations to be compared based on different fabrication and operating conditions. Through the inclusion of flexible models into the BISON framework, core designers can utilize fuel performance simulations as an additional tool to support irradiation experiments and push for novel fuel designs. (author)

Part of:
Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17). Proceedings of an International Conference. Companion CD-ROM

Additional details

Publishing Information

Publisher
IAEA
Imprint Place
Vienna (International Atomic Energy Agency (IAEA))
ISBN
978-92-0-108618-1
Imprint Title
Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17). Proceedings of an International Conference. Companion CD-ROM
Imprint Pagination
[1 CD-ROM]
Series
Proceedings Series
Journal Page Range
9 p.
ISSN
0074-1884

Conference

Title
International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development
Acronym
FR17
Dates
26-29 Jun 2017
Place
Yekaterinburg (Russian Federation)

Optional Information

Notes
11 refs., 7 figs. Imprint:refs., figs., tabs.
Secondary number(s)
IAEA-CN--245-366