skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: A Low-Enriched Uranium (LEU) option for the conversion of FRM II

Journal Article · · Annals of Nuclear Energy

The Forschungs-Neutronenquelle Heinz Maier-Leibnitz (FRM II) is Germany’s most powerful research reactor and uses Highly Enriched Uranium (HEU) fuel enriched at 93 %. The Technical University of Munich (TUM) operates the reactor and has been mandated to convert the FRM II to a lower-enrichment fuel. In preparation for the lower-enrichment fuel downselection, planned for 2023, TUM is evaluating multiple conversion scenarios. In this paper, it is demonstrated that a conversion of FRM II to Low-Enriched Uranium (LEU) is scientifically possible when using the novel monolithic U-10Mo fuel system, which is currently in the qualification process. As a research reactor, safety criteria, neutron flux distribution and cycle length are key metrics. To begin, neutronic and thermal-hydraulic models were created based on current technical drawings and relevant material properties. Specifically tailored computational methods and coupling schemes have also been developed to properly evaluate all relevant characteristics for the conversion of the FRM II reactor. Using these models and methods, a systematic parameter study was performed to explore the defined design space. The results of that study indicate that many LEU designs using monolithic U-10Mo appear to be viable to convert FRM II to LEU. One example of an LEU solution for the FRM II reactor that fulfills the stated safety, compatibility and scientific performance requirements is discussed in more detail.

Research Organization:
Argonne National Laboratory (ANL), Argonne, IL (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation
Grant/Contract Number:
AC02-06CH11357
OSTI ID:
1991380
Journal Information:
Annals of Nuclear Energy, Vol. 183; ISSN 0306-4549
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (12)

Fuel element design and analysis for potential LEU conversion of the Advanced Test Reactor journal April 2018
The Determination of Forced-Convection Surface-Boiling Heat Transfer journal August 1964
IRRADIATION PERFORMANCE OF U-Mo MONOLITHIC FUEL journal April 2014
New energy deposition treatment in the Serpent 2 Monte Carlo transport code journal July 2019
Heat Transfer and Pressure Drop of Liquids in Tubes journal December 1936
Turbulent flow in Pipes, with Particular Reference to the Transition Region Between the Smooth and Rough pipe Laws. journal February 1939
The Serpent Monte Carlo code: Status, development and applications in 2013 journal August 2015
serpentTools: A Python Package for Expediting Analysis with Serpent journal March 2020
SLOWPOKE-2 alternative core loading configurations analysis for highly improved reactor performance journal June 2019
First Steps to Coupled Hydraulic and Mechanical Calculations Within a Parameter Study to Define Possible core Designs for the Conversion of frm ii journal January 2021
Non-destructive analysis of swelling in the EMPIrE fuel test journal June 2022
On the Dynamical Theory of Incompressible Viscous Fluids and the Determination of the Criterion journal January 1895

Similar Records

Involute Working Group – Validation of CFD Turbulence Models for Steady-State Safety Analysis
Technical Report · Wed Jan 01 00:00:00 EST 2020 · OSTI ID:1991380

An alternative LEU design for the FRM-II
Conference · Sat Feb 01 00:00:00 EST 1997 · OSTI ID:1991380

Alternative LEU design for the FRM-II
Journal Article · Mon Dec 01 00:00:00 EST 1997 · Transactions of the American Nuclear Society · OSTI ID:1991380