Initial MCNP6 Release Overview - MCNP6 version 1.0

Goorley, John T.; James, Michael R.; Booth, Thomas E.; Bull, Jeffrey S.; Cox, L. J.; Durkee, Joe W.; Elson, Jay S.; Fensin, Michael L; Forster, Robert; Hendricks, John S.; Hughes, H.G.; Johns, Russell C.; Kiedrowski, Brian C.; Martz, Roger L.; Mashnik, S. G.; McKinney, G.W.; Pelowitz, Denise B.; Prael, R.E.; Sweezy, Jeremy; Waters, L.; Wilcox, Trevor; Zukaitis, Anthony J.

doi:10.2172/1086758

Cited by 341 publications

(330 citation statements)

References 7 publications

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“…While the NOB and MOB algorithms are implemented in the power method, the superhistory algorithm is implemented in the superhistory method. The new capability in RMC has been verified and validated by comparison to MCNP6 (Goorley et al, 2013) and experimental results through a set of multi-group problems and continuousenergy problems (Kiedrowski, 2010;Mosteller and Kiedrowski, 2011) covering a wide range of uranium, plutonium and U-233 fueled experiments from fast to thermal spectrum, which are summarized in Table 1.…”

Section: Verification and Resultsmentioning

confidence: 98%

Calculation of adjoint-weighted kinetic parameters with the reactor Monte Carlo code RMC

Qiu

Wang

et al. 2017

Progress in Nuclear Energy

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a b s t r a c tIn this work, the capability of computing adjoint-weighted kinetic parameters, including effective delayed neutron fraction and neutron generation time, was implemented in the Reactor Monte Carlo (RMC) code based on the iterated fission probability (IFP) method. Three algorithms, namely, the NonOverlapping Blocks (NOB) algorithm, the Multiple Overlapping Blocks (MOB) algorithm and the superhistory algorithm, were implemented in RMC to investigate their accuracy, computational efficiency and estimation of variance. The algorithms and capability of computing kinetic parameters in RMC were verified and validated by comparison with MCNP6 as well as experimental results through a set of multigroup problems and continuous-energy problems.

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Section: Verification and Resultsmentioning

confidence: 98%

Calculation of adjoint-weighted kinetic parameters with the reactor Monte Carlo code RMC

Qiu

Wang

et al. 2017

Progress in Nuclear Energy

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“…MCNP6 is a combination of the capabilities of MCNP5 and MCNPX, as well as the further development of both of these codes by groups at Los Alamos National Laboratory, where neutron transport codes have been developed since the 1950s [20]. Later development of photon transport codes, and the merger of the two lead to the release of the MCNP3 (originally Monte Carlo Neutron Photon, now Monte Carlo N-Particle) in 1983.…”

Section: A Mcnpmentioning

confidence: 99%

Comparison of CdZnTe neutron detector models using MCNP6 and Geant4

et al. 2018

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Abstract-The production of accurate detector models is of high importance in the development and use of detectors. Initially, MCNP and Geant were developed to specialise in neutral particle models and accelerator models, respectively; there is now a greater overlap of the capabilities of both, and it is therefore useful to produce comparative models to evaluate detector characteristics. In a collaboration between Lancaster University, UK, and Innovative Physics Ltd., UK, models have been developed in both MCNP6 and Geant4 of Cadmium Zinc Telluride (CdZnTe) detectors developed by Innovative Physics Ltd. Herein, a comparison is made of the relative strengths of MCNP6 and Geant4 for modelling neutron flux and secondary γ-ray emission. Given the increasing overlap of the modelling capabilities of MCNP6 and Geant4, it is worthwhile to comment on differences in results for simulations which have similarities in terms of geometries and source configurations.

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“…This step requires the description of the angular and energetic distributions of the X-ray source. A Monte Carlo computation is needed using the MCNP-6 code [6], describing the electron beam and conversion target. The calculation is done once for all for a given LINAC.…”

Section: A Simulation In Cone-beam Radiographymentioning

confidence: 99%

Fast high-energy X-ray imaging for Severe Accidents experiments on the future PLINIUS-2 platform

Berge¹,

Estre²,

Tisseur³

et al. 2018

EPJ Web Conf.

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Abstract-The future PLINIUS-2 platform of CEA Cadarache will be dedicated to the study of corium interactions in severe nuclear accidents, and will host innovative large-scale experiments. The Nuclear Measurement Laboratory of CEA Cadarache is in charge of real-time high-energy X-ray imaging set-ups, for the study of the corium-water and corium-sodium interaction, and of the corium stratification process. Imaging such large and high-density objects requires a 15 MeV linear electron accelerator coupled to a tungsten target creating a highenergy Bremsstrahlung X-ray flux, with corresponding dose rate about 100 Gy/min at 1 m. The signal is detected by phosphor screens coupled to high-framerate scientific CMOS cameras. The imaging set-up is established using an experimentally-validated home-made simulation software (MODHERATO). The code computes quantitative radiographic signals from the description of the source, object geometry and composition, detector, and geometrical configuration (magnification factor, etc.). It accounts for several noise sources (photonic and electronic noises, swank and readout noise), and for image blur due to the source spot-size and to the detector unsharpness. In a view to PLINIUS-2, the simulation has been improved to account for the scattered flux, which is expected to be significant. The paper presents the scattered flux calculation using the MCNP transport code, and its integration into the MODHERATO simulation. Then the validation of the improved simulation is presented, through confrontation to real measurement images taken on a small-scale equivalent set-up on the PLINIUS platform. Excellent agreement is achieved. This improved simulation is therefore being used to design the PLINIUS-2 imaging set-ups (source, detectors, cameras, etc.).

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Initial MCNP6 Release Overview - MCNP6 version 1.0

Cited by 341 publications

References 7 publications

Calculation of adjoint-weighted kinetic parameters with the reactor Monte Carlo code RMC

Calculation of adjoint-weighted kinetic parameters with the reactor Monte Carlo code RMC

Comparison of CdZnTe neutron detector models using MCNP6 and Geant4

Fast high-energy X-ray imaging for Severe Accidents experiments on the future PLINIUS-2 platform

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