Open Access
Comparison of the FRM-II HEU design with an alternative LEU design
S.C. Mo,N.A. Hanan,J.E. Matos +2 more
TLDR
In this article, an alternative core design utilizing low-enriched uranium (LEU, <20%) silicide fuel with 4.8 g/cm{sup 3} that provides nearly the same neutron flux for experiments as the HEU design, but has a less favorable fuel cycle economy.Abstract:
The FRM-II reactor design of the Technical University of Munich has a compact core that utilizes fuel plates containing highly-enriched uranium (HEU, 93%). This paper presents an alternative core design utilizing low-enriched uranium (LEU, <20%) silicide fuel with 4.8 g/cm{sup 3} that provides nearly the same neutron flux for experiments as the HEU design, but has a less favorable fuel cycle economy. If an LEU fuel with a uranium density of 6.0 - 6.5 g/cm{sup 3} were developed, the alternative design would provide the same neutron flux and use the same number of cores per year as the HEU design. The results of this study show that there are attractive possibilities for using LEU fuel instead of HEU fuel in the FRM-II. Further optimization of the LEU design and near-term availability of LEU fuel with a uranium density greater than 4.8 g/cm{sup 3} would enhance the performance of the LEU core. The RERTR Program is ready to exchange information with the Technical University of Munich to resolve any differences that may exist and to identify design modifications that would optimize reactor performance utilizing LEU fuel.read more
Citations
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Modeling of the High Flux Isotope Reactor Cycle 400
Ned Xoubi,R. T. Primm +1 more
TL;DR: This document summarizes current capabilities, research and operational priorities, and plans for further studies that were established at the 2015 USGS workshop on quantitative hazard assessments of earthquake-triggered landsliding and liquefaction in the Central American region.
Journal ArticleDOI
The Conversion of Research Reactors to Low-Enriched Fuel and the Case of the FRM-II
TL;DR: The use of highly enriched uranium (HEU) as fuel in research reactors runs contrary to the concept of proliferation-resistant nuclear technologies as mentioned in this paper, and international activities have been undertaken to terminate the use of HEU in research as mentioned in this paper by supporting the conversion of these facilities to low-enriched uranium.
Journal Article
An alternative LEU design for the FRM-II
TL;DR: The low-enriched uranium (LEU) design proposed by the Reduced Enrichment Research and Test Reactor (RERTR) Program at Argonne National Laboratory (ANL) has a compact core consisting of a single fuel element that uses LEU (<20%) silicide fuel with 4.5 g U/cm{sup 3} and operates at 32 MW as discussed by the authors.
Construction of a sputtering reactor for the coating and processing of monolithic U-Mo nuclear fuel
TL;DR: In this paper, sputter deposition was used for the first time to coat monolithic U-Mo nuclear fuel foils with diffusion inhibitive materials, which prevented the formation of an interdiffusion layer between UMo and Al cladding during the use of the fuel.
Dissertation
Neutronics Calculations Relevant to the Conversion of Research Reactors to Low-Enriched Fuel
TL;DR: In this paper, a new computational tool for neutronics calculations (M3O) is presented, which is based on standard physics codes, while using the technical computing environment Mathematica as the primary user interface.
References
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MCNP-A General Monte Carlo N-Particle Transport Code
TL;DR: In this article, the authors present a practical guide for the use of general-purpose Monte Carlo code MCNP, including several examples and a discussion of the particular techniques and the Monte Carlo method itself.
ReportDOI
User's guide for the REBUS-3 fuel cycle analysis capability
TL;DR: This new capability is an extension and refinement of the REBUS-3 code system and complies with the standard code practices and interface dataset specifications of the Committee on Computer Code Coordination (CCCC).
Journal ArticleDOI
Reactor design of the advanced neutron source
TL;DR: The Advanced Neutron Source (ANS) as discussed by the authors was designed for materials sciences, isotope production, and fundamental physics research, and achieved a peak thermal neutron flux over five times higher than that in use at any currently operating steady-state facility.
ReportDOI
Fuel plate stability experiments and analysis for the Advanced Neutron Source
TL;DR: The planned Advanced Neutron Source (ANS) as mentioned in this paper will use closely spaced arrays of involute-shaped fuel plates that will be cooled by water flowing through the channels between the plates, and there is concern that at certain coolant flow velocities, adjacent plates may deflect and touch, with resulting failure of the plates.
ReportDOI
Analysis of hydraulic instability of ANS involute fuel plates
TL;DR: In this paper, the curved shell equations for the involute Advanced Neutron Source (ANS) fuel plates are coupled to two-dimensional hydraulic channel flow equations that include fluid friction and a complete set of fluid and plate boundary conditions is applied at the entrance and exit and along the sides of the plate and the channel.
Related Papers (5)
Low-Enriched Uranium Fuel Design with Two-Dimensional Grading for the High Flux Isotope Reactor
Germina Ilas,Trent Primm +1 more