Power distributions in fresh and depleted LEU and HEU cores of the MITR reactor.

Wilson, E.; Horelik, Nicholas; Dunn, F.E.; Newton, Thomas H.; Hu, Lin‐Wen; Stevens, John G.

doi:10.2172/1037973

Cited by 6 publications

(33 citation statements)

References 2 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Power distributions are generated by dividing each plate into four equal stripes along the 2.082 inch width. The four stripes were shown in [4] to represent the power peaking at the outside of each plate without explicitly taking into account lateral heat conduction. Since the lateral division is based upon this analysis, the results presented in this work are intended only for use in a thermal hydraulic analysis which does not explicitly model or otherwise incorporate the effects of lateral heat conduction.…”

Section: Calculation Methodology For Power Distributionsmentioning

confidence: 99%

“…b As illustrated in Figure 5, dimension (b). This dimension represents the limiting case of an assembly nozzle touching the adjacent structural wall as discussed in [4]. Table 2 gives the various nominal dimensions of an end channel for the limiting case, a C-ring end channel facing the core housing.…”

Section: Nominal Element Geometrymentioning

confidence: 99%

“…In order to characterize power distributions over a range of MITR LEU core configurations, a set of depleted cores was generated [4]. The most limiting case, in terms of both power and thermal hydraulics was found for a depleted MITR LEU Core 189, and is described below [3].…”

Section: Limiting Leu Power Distributionmentioning

confidence: 99%

“…The thermal hydraulic analyses of the reactor have required detailed power distributions and geometrical considerations in order to identify regions of interest for safety analyses [4]. The feasibility design referenced in [5] has been used throughout the works previously referenced.…”

Section: Introductionmentioning

confidence: 99%

See 3 more Smart Citations

Conceptual design parameters for MITR LEU-Mo fuel conversion demonstration experimental irradiations

Wilson¹,

Newton²,

Hu³

et al. 2012

Self Cite

View full text Add to dashboard Cite

The Massachusetts Institute of Technology Reactor (MITR-II) is a research reactor in Cambridge, Massachusetts designed primarily for experiments using neutron beam and in-core irradiation facilities. It delivers a neutron flux comparable to current LWR power reactors in a compact 6 MW core using Highly Enriched Uranium (HEU) fuel.In the framework of its 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 Low Enriched Uranium (LEU) fuel. A new type of LEU fuel based on an alloy of uranium and molybdenum (UMo) is expected to allow the conversion of U.S. domestic high performance reactors like the MITR-II reactor. Toward specifying requirements for Design Demonstration Experiment (DDE) Irradiations in a test reactor, a key set of conceptual design parameters are presented for MITR LEU monolithic U-Mo alloy fuel with 10 wt% Mo.

show abstract

Section: Calculation Methodology For Power Distributionsmentioning

confidence: 99%

Section: Nominal Element Geometrymentioning

confidence: 99%

Section: Limiting Leu Power Distributionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Conceptual design parameters for MITR LEU-Mo fuel conversion demonstration experimental irradiations

Wilson¹,

Newton²,

Hu³

et al. 2012

Self Cite

View full text Add to dashboard Cite

show abstract

“…Previous work has analyzed an MITR-II LEU fuel element for both performance and safety margins [1][2][3][4][5][6][7][8][9][10][11]. The reference LEU fuel considered for the conversion of MITR-II is a new type of high density Uranium-Molybdenum (UMo) alloy.…”

Section: Introductionmentioning

confidence: 99%

Low Enriched Uranium Core Design for the Massachusetts Institute of Technology Reactor (MITR) with Un-finned 12 mil-thick Clad UMo Monolithic Fuel

Bergeron¹,

Wilson²,

Yesilyurt³

et al. 2013

Self Cite

View full text Add to dashboard Cite

EXECUTIVE SUMMARYThis report contains the results of reactor fuel element design for conversion of the Massachusetts Institute of Technology Reactor (MITR) 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) and the Massachusetts Institute of Technology Nuclear Reactor Laboratory. The core conversion to LEU is being performed with financial support of the U. S. government.The goal of this work was to design an MITR LEU fuel element that could safely replace the current MITR HEU fuel element and maintain mission performance while requiring minimal, if any, changes to the reactor system. As a means to accomplish this, neutronic and steady-state thermal hydraulic performance of the MITR was analyzed with various LEU fuel element designs. The evaluation included the impact of assumed manufacturing tolerances and other uncertainties in reactor parameters.Documents that were reviewed as bases for the design and safety evaluations were the MITR design drawings and historic analyses of the facility. All of the information and data needed to construct the reactor models and perform the analyses were provided by MITR. The current HEU fuel element has 15 plates that are 0.080 inch thick with 0.010 inch deep grooves along the length of the plate. These grooves serve as fins to increase heat transfer area to the coolant. The HEU aluminide fuel contains uranium with a 235 U enrichment of 93 wt%, and is 0.030 inch thick in each plate. The Al-6061 aluminum cladding at the base of the grooves on the HEU plates is 0.015 inch thick.Prior LEU element design analyses with high-density monolithic alloy fuel have obtained equivalent performance and fuel cycle with an 18-plate element with 0.020 inch thick fuel and 0.010 inch cladding thickness (at the base of the fins). Whereas this prior MITR LEU design was based upon cladding thickness of 0.010 inch, recent manufacturing development experience has led to a re-evaluation of the minimum cladding thickness for reliable fabrication. These core and element design activities were undertaken to determine if additional cladding thickness could be incorporated into an MITR LEU element design. Since increased cladding thickness would displace water and degrade core reactivity, removal of the fins was also explored as a goal of the work. Removal of the fins would not only increase water to metal ratio in the core, but would also improve the economics of an MITR LEU element by eliminating this fabrication step, which is unique to MITR fuel design among U.S. high performance research reactors which refuel with HEU. In order to compensate for the loss of heat transfer area, an increased core coolant flow rate has been considered, and distinct fuel thicknesses were introduced in the outer plates of each element to limit heat flux peaking.The proposed LEU fuel element designs have the same over...

show abstract

RETRACTED: A new strategy to select axial power distribution for thermal hydraulic analysis

Kim

Park

2016

Annals of Nuclear Energy

View full text Add to dashboard Cite

Power distributions in fresh and depleted LEU and HEU cores of the MITR reactor.

Cited by 6 publications

References 2 publications

Conceptual design parameters for MITR LEU-Mo fuel conversion demonstration experimental irradiations

Conceptual design parameters for MITR LEU-Mo fuel conversion demonstration experimental irradiations

Low Enriched Uranium Core Design for the Massachusetts Institute of Technology Reactor (MITR) with Un-finned 12 mil-thick Clad UMo Monolithic Fuel

RETRACTED: A new strategy to select axial power distribution for thermal hydraulic analysis

Contact Info

Product

Resources

About