ADVANTG An Automated Variance Reduction Parameter Generator, Rev. 1

Mosher, Scott W.; Johnson, S. R.; Bevill, Aaron M.; Ibrahim, Ahmad; Daily, Charles R.; Evans, Thomas M.; Wagner, John C.; Johnson, J.O.; Grove, Robert E.

doi:10.2172/1210162

Cited by 72 publications

(14 citation statements)

References 10 publications

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“…These calculations are all performed with MCNP 6.2 [3], table based cross section data based on ENDF/B-VII.1 [4], and the CEM nuclear model providing cross sections above the energy range of the table based cross sections. The standard SNS/STS flux-to-dose conversion factors are used [5], and variance reduction parameters are generated using ADVANTG [6]. More details about the computer hardware and software utilized by this study are provided in APPENDIX A.…”

Section: Methodology and Modelsmentioning

confidence: 99%

Second Target Station (STS) Project: Analysis of Bunker Shielding–Preliminary Design

Miller

Mueller

Mohindroo

et al. 2022

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Section: Methodology and Modelsmentioning

confidence: 99%

Second Target Station (STS) Project: Analysis of Bunker Shielding–Preliminary Design

Miller

Mueller

Mohindroo

et al. 2022

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“…In the first step, neutron and prompt gamma-ray spectra at the opening to the KM6T line-of-sight were calculated. To obtain spectra with low statistical uncertainty, weight windows generated by code ADVANTG were used to speed up calculation [41]. In addition, the neutron and prompt gamma-ray spectra were only tallied in the direction along the KM6T line-of-sight, a 1 • spatial angle.…”

Section: Neutron Induced Gamma-ray Backgroundmentioning

confidence: 99%

Validation of realistic Monte Carlo plasma gamma-ray source on JET discharges

Žohar¹,

Nocente²,

Kos³

et al. 2022

Nucl. Fusion

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A novel modelling methodology has been developed for the creation of a realistic plasma gamma-ray source for Monte Carlo transport simulations in the tokamak JET. The methodology couples the TRANSP code for plasma transport calculations with the MCNP Monte Carlo particle transport code, thus connecting plasma physics with gamma-ray transport. This paper presents the validation of the developed source methodology by comparing calculated gamma-ray spectra with measurements performed at JET. The validation focuses on gamma-ray spectra measured by the tangential gamma-ray spectrometer during two JET three ion RF scenario discharges, performed in the JET 2019 Deuterium experimental campaign. For validation the calculated plasma gamma-ray spectrum was combined with the neutron induced prompt gamma-ray background, originating in the vacuum vessel, and scaled to absolute values calculating the total number of plasma gamma-ray and neutron emitting reactions. The comparison between calculated and measured gamma-ray spectra shows good agreement with the shape of the calculated gamma-ray spectra matching that of measurements for both studied discharges. Moreover, the calculated absolute values of the gamma-ray spectra were of the same order of magnitude at the position of the gamma-ray detector located at the end of a long line-of-sight in a biological shield. The comparison has validated the developed plasma gamma-ray source methodology for MCNP photon transport calculations at JET. The validation provides a basis for the developed plasma gamma-ray source to be used as a support for the development of future tokamaks such as DEMO.

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“…The weight-window parameters were optimized for 47 neutron energy bins covering the range [10 −5 eV-17.3 MeV]. This evaluation was performed using the ADVANTG-3.2 tool [32], which uses the deterministic code DENOVO [33]. A set of optimized weight windows for both dosimeter locations (capsule and cavity) and for all reactions was generated using the forward-weighted CADIS method [34].…”

Section: Variance Reduction and Simulation Parametersmentioning

confidence: 99%

A Detailed Analysis of the H.B. Robinson-2 Reactor Pressure Vessel Dosimetry Benchmark

et al. 2022

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The operation of many nuclear pressurized water reactors is being extended beyond their design lifetime limit. From the perspective of possible further lifetime extension, safety requirements are a priority. Therefore, the quantification of the neutron irradiation embrittlement of the reactor pressure vessel (RPV) is an important issue, as this is a guiding parameter that influences the reactor lifetime. In this context, the Institut de Radioprotection et de Sûreté Nucléaire developed a calculation scheme for the analysis of RPV aging under neutron irradiation, named VACS (vessel aging calculation scheme). VACS couples a deterministic approach (CASMO5 and SIMULATE5) to evaluate the full-core fission neutron source term and a Monte Carlo modeling (MCNP6) approach to model the neutron attenuation from the core to sites of interest (RPV, surveillance capsules, etc.). To ensure the reliability of aging predictions, this paper describes a detailed analysis of the neutron H.B. Robinson-2 reactor pressure vessel dosimetry benchmark. The results indicate that VACS shows satisfactory accuracy when the ENDF-B/VII.1 or JEFF-3.3 nuclear data libraries are used in the attenuation calculation. However, the use of ENDF-B/VIII.0 leads to significantly worse results.

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ADVANTG An Automated Variance Reduction Parameter Generator, Rev. 1

Cited by 72 publications

References 10 publications

Second Target Station (STS) Project: Analysis of Bunker Shielding–Preliminary Design

Second Target Station (STS) Project: Analysis of Bunker Shielding–Preliminary Design

Validation of realistic Monte Carlo plasma gamma-ray source on JET discharges

A Detailed Analysis of the H.B. Robinson-2 Reactor Pressure Vessel Dosimetry Benchmark

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