FW-CADIS Method for Global and Regional Variance Reduction of Monte Carlo Radiation Transport Calculations

Wagner, John C.; Peplow, Douglas E.; Mosher, Scott W.

doi:10.13182/nse12-33

Cited by 128 publications

(44 citation statements)

References 18 publications

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“…The FW-CADIS method [6] is used when more extensive Monte Carlo tally results, including mesh tallies, are required. In the FW-CADIS approach, a deterministic forward calculation is first used to generate an estimate of the flux or response of interest throughout the model phase space.…”

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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“…The MCP-N TLDs contained natural lithium with natural abundance 7.59% of 6 Li. The MCP-7 TLDs have suppressed 6 Li to 0.03% with the rest lithium content composed of to 99.97 % 7 Li. The TLD types and the current assembly were optimized on the basis of previous experience (2012-2014 DD campaigns [1]).…”

Section: Streaming Experimentsmentioning

confidence: 99%

“…Specifically ADVANTG implements the Consistent Adjoint Driven Importance Sampling (CADIS) method [6] to generate parameters to accelerate the convergence rate of an individual tally in a MCNP5 code version 1.6 [4] simulation. Alternatively, the Forward-Weighted CADIS (FW-CADIS) method [7] can be used to obtain relatively uniform rates of convergence across multiple tallies or the space and energy bins of an arbitrary sized mesh tally in a MCNP defined problem.…”

Section: Advantgmentioning

confidence: 99%

“…To differentiate between the neutron and non-neutron components of the dose field the team from the Institute of Nuclear Physics (IFJ) in Poland used two different detectors -natural and suppressed 6 Li based detectors. The highly sensitive nat LiF: Mg,Cu,P (MCP-N) and 7 LiF:Mg,Cu,P (MCP-7) TLDs. The MCP-N TLDs contained natural lithium with natural abundance 7.59% of 6 Li.…”

Section: Streaming Experimentsmentioning

confidence: 99%

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Analysis of DD, TT and DT Neutron Streaming Experiments with the ADVANTG Code

Kos¹,

Vasilopoulou

Mosher

et al. 2020

EPJ Web Conf.

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The paper presents an analysis of DD, TT and DT neutron streaming benchmark experiments with the recently released hybrid transport code ADVANTG (AutomateD VAriaNce reducTion Generator). ADVANTG combines the deterministic neutron transport solver Denovo with the Monte Carlo transport code MCNP via the principle of variance reduction. It automatically produces weight-window and source biasing variance reduction parameters based on the CADIS (Consistent Adjoint Driven Importance Sampling) methodology. Using this novel hybrid methodology Monte Carlo simulations of realistic complex fusion streaming geometries have become possible. In this paper the experimental results from the 2016 DD campaign using measurements with TLDs and activation foils up to 40 m from the plasma source are analyzed. New detailed models of the detector assemblies were incorporated into the JET 360° MCNP model for this analysis. In preparation of the TT and DTE2 campaigns at JET a pre-analysis for these campaigns is also presented.

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“…On the other hand, run 3D Monte Carlo or deterministic codes requires time which is not always compatible with the projects dead line. So, to solve this dilemma, the Oak Ridge National Laboratory (ORNL) has developed two methods for increasing the efficiency of fixed-source MC simulations: The Consistent Adjoint Driven Importance Sampling (CADIS) method [1] and the Forward Weighted CADIS (FW-CADIS) method [2]. These methods utilize the results of approximate 3-D discrete ordinates transport calculations to generate consistent space-and energy-dependent source and transport (weight windows -WW) biasing parameters for MCNP code [3].…”

Section: Introductionmentioning

confidence: 99%

Acceleration of MCNP calculations for small pipes configurations by using Weigth Windows Importance cards created by the SN-3D ATTILA

Castanier¹,

Paterne²,

Louis³

2017

EPJ Web Conf.

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Abstract. In the nuclear engineering, you have to manage time and precision. Especially in shielding design, you have to be more accurate and efficient to reduce cost (shielding thickness optimization), and for this, you use 3D codes. In this paper, we want to see if we can easily applicate the CADIS methods for design shielding of small pipes which go through large concrete walls. We assess the impact of the WW generated by the 3D-deterministic code ATTILA versus WW directly generated by MCNP (iterative and manual process). The comparison is based on the quality of the convergence (estimated relative error (

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FW-CADIS Method for Global and Regional Variance Reduction of Monte Carlo Radiation Transport Calculations

Cited by 128 publications

References 18 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*

Analysis of DD, TT and DT Neutron Streaming Experiments with the ADVANTG Code

Acceleration of MCNP calculations for small pipes configurations by using Weigth Windows Importance cards created by the SN-3D ATTILA

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