Analysis of Loss-of-Flow Accidents for the NIST Research Reactor with Fuel Conversion from HEU to LEU

2015 ◽  
Vol 189 (1) ◽  
pp. 71-86 ◽  
Author(s):  
J. S. Baek ◽  
A. Cuadra ◽  
L.-Y. Cheng ◽  
A. L. Hanson ◽  
N. R. Brown ◽  
...  
Keyword(s):  
Research Reactor ◽  
Fuel Conversion

scholarly journals Startup, transition core, and molybdenum-99 production upgrade analyses for low-enriched uranium fuel conversion at the University of Missouri research reactor

2020 ◽  
Author(s):  
◽  
Wilson Cowherd
Keyword(s):  
Low Power ◽  
Research Reactor ◽  
The United States ◽  
Fuel Conversion ◽  
Reactor Physics ◽  
University Of Missouri ◽  
Safety Margins ◽  
Enriched Uranium ◽  
The University ◽  
The Impact

Under the direction of the United States Department of Energy (DOE) National Nuclear Security Administration (NNSA) Office of Material Management and Minimization (M3) Reactor Conversion Program, the University of Missouri Research Reactor (MURR®) plans to convert from highly enriched uranium (HEU) fuel to low-enriched uranium (LEU) fuel. Low power physics startup test predictions, transition core planning, and analysis for a proposed fission-based molybdenum-99 production upgrade were done in support of LEU fuel conversion. As a first step to LEU fuel conversion, low-power physics tests will be performed to calculate reactor physics parameters. These parameters include flux distributions, coefficients of reactivity, and critical assembly measurements. To facilitate this test, reactor physics calculations were performed using MCNP5 to predict the values of these parameters. Implications of these predictions and areas of uncertainty in the prediction analysis are also discussed. Once MURR completes the testing of the initial LEU core, MURR will enter into a series of transition cycles until steady-state mixed-burnup operation is reached. A Python program was developed that incorporated the constraints of MURR operation while minimizing the time MURR will have to operate atypically during the transition cycles. The impacts of the transition cycles on experiment performance are reported, as well as the number of fuel elements needed. Finally, preliminary analysis on a proposed molybdenum-99 production device at MURR was performed. This analysis shows the impact on the reactor power distribution with implications to predicted safety margins as a part of the larger scope of the experiment analysis.

scholarly journals Transition Core Analysis for HEU to LEU Fuel Conversion at the University of Missouri Research Reactor

2020 ◽  
pp. 1-15
Author(s):  
Wilson Cowherd ◽  
John Stillman ◽  
John Gahl ◽  
Leslie Foyto ◽  
Erik Wilson
Keyword(s):  
Research Reactor ◽  
Core Analysis ◽  
Fuel Conversion ◽  
University Of Missouri ◽  
The University

scholarly journals Accident Analysis for the NIST Research Reactor Before and After Fuel Conversion

2012 ◽  
Author(s):  
Baek J. ◽  
Diamond D. ◽  
A. Cuadra ◽  
A.L. Hanson ◽  
L-Y. Cheng ◽  
...  
Keyword(s):  
Research Reactor ◽  
Accident Analysis ◽  
Fuel Conversion ◽  
Before And After

Investigation of neutronic and safety parameters variation in 5 MW research reactor due to U3O8Al fuel conversion to ThO2 + U3O8Al

Kerntechnik ◽  
2017 ◽  
Vol 82 (2) ◽  
pp. 217-224
Author(s):  
Z. Gholamzadeh ◽  
S. A. H. Feghhi ◽  
Z. Alipoor ◽  
M. Vahedi ◽  
S. M. Mirvakili ◽  
...  
Keyword(s):  
Research Reactor ◽  
Fuel Conversion ◽  
Safety Parameters

Analysis of Reactivity Insertion Accidents for the NIST Research Reactor before and after Fuel Conversion

2014 ◽  
Vol 185 (1) ◽  
pp. 1-20 ◽  
Author(s):  
J. S. Baek ◽  
A. Cuadra ◽  
L.-Y. Cheng ◽  
A. L. Hanson ◽  
N. R. Brown ◽  
...  
Keyword(s):  
Research Reactor ◽  
Fuel Conversion ◽  
Before And After ◽  
Reactivity Insertion

scholarly journals AN APPLICATION OF IRIDM IN THE DECISION MAKING PROCESS ON FUEL CONVERSION OF THE MARIA REACTOR

2013 ◽  
Vol 3 (3) ◽  
pp. 3-6 ◽  
Author(s):  
Mieczysław Józef Borysiewicz ◽  
Karol Kowal ◽  
Piotr Andrzej Prusiński ◽  
Marcin Dąbrowski
Keyword(s):  
Decision Making ◽  
Research Reactor ◽  
Nuclear Research ◽  
Decision Making Process ◽  
Fuel Conversion ◽  
National Centre ◽  
Uranium Fuel ◽  
Integrated Risk ◽  
Enriched Uranium ◽  
Global Threat

Poland, when acceded to GTRI (Global Threat Reduction Initiative) in 2004, has committed to convert the nuclear fuel of the Research Reactor MARIA, operated by the National Centre for Nuclear Research (NCBJ) in Świerk. The conversion means giving up of high enriched uranium fuel containing 36% of U-235, which was used so far, and replacing it with the low enriched uranium fuel (19.7% U-235). This article describes the potential usability of the Integrated Risk Informed Decision Making (IRIDM) methodology in optimization of the fuel conversion procedure.

scholarly journals MARIA Reactor Irradiation Technology Capabilities towards Advanced Applications

Energies ◽  
2021 ◽  
Vol 14 (23) ◽  
pp. 8153
Author(s):  
Marek Migdal ◽  
Emilia Balcer ◽  
Łukasz Bartosik ◽  
Łukasz Bąk ◽  
Agnieszka Celińska ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Scientific Community ◽  
Research Reactor ◽  
Nuclear Research ◽  
Material Testing ◽  
Reactor Irradiation ◽  
Fuel Conversion ◽  
Nuclear Installation ◽  
Power Studies ◽  
Irradiation Technology

The MARIA research reactor is designed and operated as a multipurpose nuclear installation, combining material testing, neutron beam experiments, and medical and industrial radionuclide production, including molybdenum-99 (99Mo). Recently, after fuel conversion to LEU and rejuvenation of the staff while maintaining their experience, MARIA has been used to respond to the increased interest of the scientific community in advanced nuclear power studies, both fission and fusion. In this work, we would like to introduce MARIA’ s capabilities in the irradiation technology field and how it can serve future nuclear research worldwide.

Sign in / Sign up

Export Citation Format

Share Document