Neutron and Gamma Fluxes and dpa Rates for HFIR Vessel Beltline Region (Present and Upgrade Designs)

Blakeman, E.D.

doi:10.2172/777683

Cited by 6 publications

(9 citation statements)

References 3 publications

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“…Previous analyses of neutron and photon dpa rates [1,2] for HFIR were generally performed using a combination of two-dimensional (2D) and three-dimensional (3D) discrete ordinates calculations. While that methodology was reasonable for the relatively small set of dpa locations that were analyzed for many years, it was limited by the discretization errors that affect the accuracy that can be obtained using a deterministic analysis (i.e., the approximations inherent in the use of spatial mesh, discrete ordinates, and multigroup cross sections to represent the continuous space, direction, and energy variables).…”

Section: Epj Web Of Conferencesmentioning

confidence: 99%

Analysis of dpa Rates in the HFIR Reactor Vessel using a Hybrid Monte Carlo/Deterministic Method*

Risner

Blakeman

2016

EPJ Web of Conferences

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Abstract. The Oak Ridge High Flux Isotope Reactor (HFIR), which began full-power operation in 1966, provides one of the highest steady-state neutron flux levels of any research reactor in the world. An ongoing vessel integrity analysis program to assess radiation-induced embrittlement of the HFIR reactor vessel requires the calculation of neutron and gamma displacements per atom (dpa), particularly at locations near the beam tube nozzles, where radiation streaming effects are most pronounced. In this study we apply the Forward-Weighted Consistent Adjoint Driven Importance Sampling (FW-CADIS) technique in the ADVANTG code to develop variance reduction parameters for use in the MCNP radiation transport code. We initially evaluated dpa rates for dosimetry capsule locations, regions in the vicinity of the HB-2 beamline, and the vessel beltline region. We then extended the study to provide dpa rate maps using three-dimensional cylindrical mesh tallies that extend from approximately 12 in. below to approximately 12 in. above the height of the core. The mesh tally structures contain over 15,000 mesh cells, providing a detailed spatial map of neutron and photon dpa rates at all locations of interest. Relative errors in the mesh tally cells are typically less than 1%.

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Section: Epj Web Of Conferencesmentioning

confidence: 99%

Analysis of dpa Rates in the HFIR Reactor Vessel using a Hybrid Monte Carlo/Deterministic Method*

Risner

Blakeman

2016

EPJ Web of Conferences

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“…Here mainly for methodological verification, we also employed dpa (displacements per atom), both neutron-induced [17] and -induced (for Fe only, Table 3 in [18] -note that the threshold is 700 keV). The three vertical positions where the PV damage is evaluated are shown in Fig.…”

Section: Pwr Gen III With Thick Steel Reflectormentioning

confidence: 99%

On integrating Monte Carlo calculations in and around near-critical configurations – II. Pressurized water reactors

Brovchenko

Burn

Camprini

2023

Annals of Nuclear Energy

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“…6,13,14 The calculated neutron and gamma fluxes are listed in Appendix B. The LSL-M2 15 computer code package was used to perform neutron and gamma spectrum adjustment calculations and other required data conversions and/or manipulations.…”

Section: 12mentioning

confidence: 99%

Analysis of HFIR Dosimetry Experiments Performed in Cycles 400 and 401

Remec¹,

Baldwin

2008

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Neutron and Gamma Fluxes and dpa Rates for HFIR Vessel Beltline Region (Present and Upgrade Designs)

Cited by 6 publications

References 3 publications

Analysis of dpa Rates in the HFIR Reactor Vessel using a Hybrid Monte Carlo/Deterministic Method*

Analysis of dpa Rates in the HFIR Reactor Vessel using a Hybrid Monte Carlo/Deterministic Method*

On integrating Monte Carlo calculations in and around near-critical configurations – II. Pressurized water reactors

Analysis of HFIR Dosimetry Experiments Performed in Cycles 400 and 401

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