Thermal properties for the thermal-hydraulics analyses of the BR2 maximum nominal heat flux.

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This memo describes the assumptions and references used in determining the thermal properties for the various materials used in the BR2 HEU (93% enriched in {sup 235}U) to LEU (19.75% enriched in {sup 235}U) conversion feasibility analysis. More specifically, this memo focuses on the materials contained within the pressure vessel (PV), i.e., the materials that are most relevant to the study of impact of the change of fuel from HEU to LEU. This section is regrouping all of the thermal property tables. Section 2 provides a summary of the thermal properties in form of tables while the following sections present ... continued below

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Dionne, B.; Kim, Y. S. & Hofman, G. L. (Nuclear Engineering Division) May 23, 2011.

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Description

This memo describes the assumptions and references used in determining the thermal properties for the various materials used in the BR2 HEU (93% enriched in {sup 235}U) to LEU (19.75% enriched in {sup 235}U) conversion feasibility analysis. More specifically, this memo focuses on the materials contained within the pressure vessel (PV), i.e., the materials that are most relevant to the study of impact of the change of fuel from HEU to LEU. This section is regrouping all of the thermal property tables. Section 2 provides a summary of the thermal properties in form of tables while the following sections present the justification of these values. Section 3 presents a brief background on the approach used to evaluate the thermal properties of the dispersion fuel meat and specific heat capacity. Sections 4 to 7 discuss the material properties for the following materials: (i) aluminum, (ii) dispersion fuel meat (UAlx-Al and U-7Mo-Al), (iii) beryllium, and (iv) stainless steel. Section 8 discusses the impact of irradiation on material properties. Section 9 summarizes the material properties for typical operating temperatures. Appendix A elaborates on how to calculate dispersed phase's volume fraction. Appendix B shows the evolution of the BR2 maximum heat flux with burnup.

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  • Report No.: ANL/RERTR/TM-11-20
  • Grant Number: DE-AC02-06CH11357
  • DOI: 10.2172/1018508 | External Link
  • Office of Scientific & Technical Information Report Number: 1018508
  • Archival Resource Key: ark:/67531/metadc838152

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  • May 23, 2011

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  • May 19, 2016, 3:16 p.m.

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  • May 23, 2016, 6:22 p.m.

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Dionne, B.; Kim, Y. S. & Hofman, G. L. (Nuclear Engineering Division). Thermal properties for the thermal-hydraulics analyses of the BR2 maximum nominal heat flux., report, May 23, 2011; United States. (digital.library.unt.edu/ark:/67531/metadc838152/: accessed July 17, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.