Preliminary Accident Analyses for Conversion of the University of Missouri Research Reactor (MURR) from Highly-Enriched to Low-Enriched Uranium Prepared by

Feldman, E.E.; Foyto, L.; Kutikkad, K.; McKibben, J.C.; Peters, N. J.; Stevens, John G.; Stillman, J. A.; Wilson, E.

doi:10.2172/1087294

Cited by 2 publications

(14 citation statements)

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“…U-10Mo swelling due to irradiation given in equation 4.2 is considered in the HFIR [3] and MITR [6] reports. Fuel swelling is also discussed in work for MURR [4,90] that considers channel restriction at end of life of 8 mil from all sources, which was derived based on the same equation. Analyses for ATR [7] As a note, the "x10 21 " term should be discarded, as the fission densities are in fissions/cm 3 .…”

Section: Fuel Swelling Comparison Of the Correlations Utilized In Anamentioning

confidence: 99%

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Review of the Technical Basis for Properties and Fuel Performance Data Used in HEU to LEU Conversion Analysis for U-10Mo Monolithic Alloy Fuel

Jamison

Stillman

Jalůvka

et al. 2020

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Section: Fuel Swelling Comparison Of the Correlations Utilized In Anamentioning

confidence: 99%

“…For a detailed discussion of these correlations and values, see the section number referenced to under the Property header. MURR Channel closure of 8mil after fabrication [4,90] NBSR ∆ 0 (%) = 0.5700 2 + 4.300 [91]…”

Section: Appendix D: Summary Of Materials Propertiesmentioning

confidence: 99%

Review of the Technical Basis for Properties and Fuel Performance Data Used in HEU to LEU Conversion Analysis for U-10Mo Monolithic Alloy Fuel

Jamison

Stillman

Jalůvka

et al. 2020

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“…The PARET/ANL model parameters employed in the MURR SAR were examined in detail and updated with appropriate values for both HEU and LEU fueled cores in a previous analysis [4]. Specifically, the PARET/ANL model was revised to utilize reactivity feedback coefficients, detailed power distributions, and control bank worths for the reactor safety system that were calculated for HEU and LEU fueled cores with a detailed MCNP5 [14] core model.…”

Section: Reactivity Insertion Accidentsmentioning

confidence: 99%

“…Preliminary analyses of those accident scenarios that have been most challenging to fuel integrity were previously completed for cores loaded with LEU U-10Mo fuel elements [4]. These "Phase I" analyses for reactivity insertion (RIA), loss-of-coolant (LOCA), and loss-of-flow (LOFA) accidents predicted peak fuel centerline temperatures that were well below preliminary measurements of the blister temperature for the proposed monolithic LEU fuel type, but only fresh fuel plates were considered.…”

Section: Anl/gtri/tm-14/5mentioning

confidence: 99%

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Accident Analyses for Conversion of the University of Missouri Research Reactor (MURR) from Highly-Enriched to Low-Enriched Uranium

Stillman

Feldman

Wilson

et al. 2014

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This report contains the results of reactor accident analyses for the University of Missouri Research Reactor (MURR). The calculations were performed as part of the conversion from the use of highly-enriched uranium (HEU) fuel to the use of low-enriched uranium (LEU) fuel. The analyses were performed by staff members of the Global Threat Reduction Initiative (GTRI) Reactor Conversion Program at the Argonne National Laboratory (ANL), the MURR Facility, and the Nuclear Engineering Program -College of Engineering, University of Missouri-Columbia. The core conversion to LEU is being performed with financial support from the U. S. government.In the framework of non-proliferation policies, the international community presently aims to minimize the amount of nuclear material available that could be used for nuclear weapons. In this geopolitical context most research and test reactors, both domestic and international, have started a program of conversion to the use of LEU fuel. A new type of LEU fuel based on an alloy of uranium and molybdenum (U-Mo) is expected to allow the conversion of U.S. domestic high performance reactors like MURR. This report presents the results of a study of core behavior under a set of accident conditions for MURR cores fueled with HEU U-Al x dispersion fuel or LEU monolithic U-Mo alloy fuel with 10 wt% Mo (U-10Mo).For the proposed LEU-fueled core, previous studies [1] have shown that in order to maintain the neutron flux at various crucial experimental locations within the reactor at the same level after the fuel conversion from the HEU to LEU, the steady-state operating power level must be increased from 10 MW to 12 MW. Hence, the accidental positive reactivity insertions, and the loss-of-coolant and loss-of-flow accidents for the LEU core were initiated from an initial steadystate power level of 12 MW. It is noted that all references to the core power level for MURR in this report are the thermal power output of the reactor (i.e., MWt).A search of the published literature and available technical reports was conducted to obtain appropriate values of thermal conductivity and volumetric heat capacity for the materials of 1) the irradiated and unirradiated HEU and LEU fuel meat, 2) the zirconium layers in the LEU fuel plates, 3) the 6061-aluminum of the fuel plate cladding, the reactor vessel walls, and primary system pipes, and 4) the oxide layer on the cladding surfaces of the irradiated fuel plates. This set of material properties was used in the analyses of the reactivity insertion accidents (RIA), loss-of-coolant accidents (LOCA), and loss-of-flow accidents (LOFA).The transient simulations of RIAs, LOCAs, and LOFAs are initiated from the conservative end of the normal operating band for reactor power, reactor primary coolant flow, and reactor core inlet temperature. The typical core state for the MURR was assumed in these simulations. This state has elements with a mixture of burnups, the flux trap is loaded with irradiation samples and experiments, and the control blades are banked in the...

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Preliminary Accident Analyses for Conversion of the University of Missouri Research Reactor (MURR) from Highly-Enriched to Low-Enriched Uranium Prepared by

Cited by 2 publications

References 5 publications

Review of the Technical Basis for Properties and Fuel Performance Data Used in HEU to LEU Conversion Analysis for U-10Mo Monolithic Alloy Fuel

Review of the Technical Basis for Properties and Fuel Performance Data Used in HEU to LEU Conversion Analysis for U-10Mo Monolithic Alloy Fuel

Accident Analyses for Conversion of the University of Missouri Research Reactor (MURR) from Highly-Enriched to Low-Enriched Uranium

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