Design Study for a Low-Enriched Uranium Core for the High Flux Isotope Reactor, Annual Report for FY 2008

Primm, Trent; Chandler, David W.; Ilas, Germina; Miller, James H.; Sease, J.D.; Jolly, Brian

doi:10.2172/950437

Cited by 7 publications

(2 citation statements)

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“…Currently the reference model used to perform analyses in support of HFIR operation is a Monte Carlo N-Particle (MCNP) [2] model of HFIR Cycle 400 that was documented in 2005 [3]. This model has been slightly revised [4,5] to enable Monte Carlo-based depletion simulations for the HFIR core. This revision has served as a basis for extensive HFIR validation studies [6,7].…”

Section: Introductionmentioning

confidence: 99%

Modeling and Simulations for the High Flux Isotope Reactor Cycle 400

Ilas

Chandler

Ade

et al. 2015

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A concerted effort over the past few years has been focused on enhancing the core model for the High Flux Isotope Reactor (HFIR), as part of a comprehensive study for HFIR conversion from high-enriched uranium to low-enriched uranium (LEU) fuel. At this time, the core model used to perform analyses in support of HFIR operation is a Monte Carlo model with the MCNP code for the beginning of Cycle 400, which was documented in detail in a 2005 technical report. An updated HFIR core depletion model that is based on current state-of-the-art methods and nuclear data was needed to serve as reference for the design of an LEU fuel for HFIR.The recent enhancements in modeling and simulations for HFIR that are discussed in the present report include: (1) revision of the 2005 MCNP model for the beginning of Cycle 400 to improve the modeling data and assumptions as necessary based on appropriate primary reference sources-HFIR drawings and reports; (2) improvement of the fuel region model, including an explicit representation for the involute fuel plate geometry that is specific to HFIR fuel; and (3) revision of the Monte Carlo-based depletion model for HFIR, in use since 2009 but never documented in detail, with the development of a new depletion model for the HFIR explicit fuel plate representation.The new HFIR models for Cycle 400 are used to determine various metrics of relevance to reactor performance and safety assessments. The calculated metrics are compared, where possible, with measurement data from preconstruction critical experiments at HFIR, data included in the current HFIR safety analysis report, and/or data from previous calculations performed with different methods or codes. The results of the analyses show that the models presented in this report provide a robust and reliable basis for HFIR analyses.

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Section: Introductionmentioning

confidence: 99%

Modeling and Simulations for the High Flux Isotope Reactor Cycle 400

Ilas

Chandler

Ade

et al. 2015

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“…As described in Ilas and Primm [1], VESTA can be used to couple a variety of transport codes, including MCNP, to the ORIGEN2.2 [22] depletion code. However, because highly detailed and validated 3D MCNP models existed for prior HFIR HEU analyses [23], these models were used in VESTA as the starting point to develop the proposed LEU core design of Ilas and Primm [1]. Material compositions from the first (BOC) and last time (EOC) steps of the Ilas and Primm [1] design study have been used for the current LEU RV dpa rate analyses.…”

Section: Depletion Methodsmentioning

confidence: 99%