Initial MCNP6 Release Overview

Goorley, Tim; James, Michael R.; Booth, Thomas E.; Brown, Forrest B.; 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, T.

doi:10.13182/nt11-135

Cited by 1,001 publications

(539 citation statements)

References 23 publications

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“…MCNP6 as a Monte Carlo code and ENDF/B-VII.1 as an evaluated nuclear data library were used for simulating the photonuclear reaction in the target [14,15]. Figure 3 shows the calculation model of the present study.…”

Section: Calculation Model and Methodsologymentioning

confidence: 99%

Precision requirement of the photofission cross section for the nondestructive assay

2017

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Abstract. Principle of the new NDA technique based on the photofission reaction rate ratio (PFRR) has been developed by Kimura et al for measurement of uranium enrichment by using the only relative measured counts of neutron produced by photofission reactions of 235 U and 238 U at different specific incident photon energies. In the past analysis, no attentions have been paid for relatively large uncertainty of photonuclear cross section of special nuclear materials around 10%. In the present paper, quantitative analysis was performed to reveal the impact of photonuclear cross section uncertainty to predicted value of the uranium enrichment by the PFRR methodology. And also, the requirement of photofission cross section precision was evaluated as less than 3%, to satisfy the uncertainty of PFRR methodology to within 5%.

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Section: Calculation Model and Methodsologymentioning

confidence: 99%

Precision requirement of the photofission cross section for the nondestructive assay

2017

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“…MCNP Monte Carlo Code [21] calculations of the attenuation due to this shield have been carried out. The attenuation of the neutron flux, and associated heat deposition in the central core, as a function of shield thickness have been param eterised and included in the TE System Code [20].…”

Section: Shielding Energy Deposition Neutron Flux and Damage In Thementioning

confidence: 99%

Compact fusion energy based on the spherical tokamak

et al. 2017

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“…The efficiency calibration of the HPGe detector was calculated using the MCNP6 code [10]. The measured spectra were analyzed by Genie 2000 software.…”

Section: Gamma Spectroscopy Detailsmentioning

confidence: 99%

Measurement of the²³Na(n,2n) cross section in²³⁵U and²⁵²Cf fission neutron spectra

et al. 2017

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Abstract. The presented paper aims to compare the calculated and experimental reaction rates of 23 Na(n,2n) 22 Na in a well-defined reactor spectra and in the spontaneous fission spectrum of 252 Cf. The experimentally determined reaction rate, derived using gamma spectroscopy of irradiated NaF sample, is used for average cross section determination.Estimation of this cross-section is important as it is included in International Reactor Dosimetry and Fusion File and is also relevant to the correct estimation of longterm activity of Na coolant in Sodium Fast Reactors. The calculations were performed with the MCNP6 code using ENDF/B-VII.0, JEFF-3

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Initial MCNP6 Release Overview

Cited by 1,001 publications

References 23 publications

Precision requirement of the photofission cross section for the nondestructive assay

Precision requirement of the photofission cross section for the nondestructive assay

Compact fusion energy based on the spherical tokamak

Measurement of the²³Na(n,2n) cross section in²³⁵U and²⁵²Cf fission neutron spectra

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Initial MCNP6 Release Overview

Cited by 1,001 publications

References 23 publications

Precision requirement of the photofission cross section for the nondestructive assay

Precision requirement of the photofission cross section for the nondestructive assay

Compact fusion energy based on the spherical tokamak

Measurement of the23Na(n,2n) cross section in235U and252Cf fission neutron spectra

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Product

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Measurement of the²³Na(n,2n) cross section in²³⁵U and²⁵²Cf fission neutron spectra