Results 61 to 70 of about 8,745 (215)

MOCUP: MCNP-ORIGEN2 coupled utility program [PDF]

, 1995
MOCUP is a system of external processors that allow for a limited treatment of the temporal composition of the user-selected MCNP cells in a time-dependent flux environment.
Wemple, C. A., Moore, R. L., Schnitzler, B. G.   +2 more
core   +1 more source

Simulating neutron protein crystallography experiments: applications to the development of the NMX instrument at ESS

Acta Crystallographica Section D, Volume 82, Issue 7, Page 751-760, July 2026.
Monte Carlo simulations of neutron protein diffraction experiments provide useful data that models neutrons interacting with instrument components, as well as the crystal diffraction itself. These data can be applied to instrument development, such as the commissioning of the NMX Macromolecular Diffractometer at ESS.Monte Carlo neutron ray‐tracing ...
Mads Bertelsen, Peter K. Willendrup, Sunyoung Yoo, Adriano Meligrana, David McDonagh, Justin Bergmann, Esko Oksanen, Aaron D. Finke   +7 more
wiley   +1 more source

MCNP variance reduction overview [PDF]

, 2006
The MCNP code is rich in variance reduction features. Standard variance reduction methods found in most Monte Carlo codes are available as well as a number of methods unique to MCNP. We discuss the variance reduction features presently in MCNP as well as new ones under study for possible inclusion in future versions of the code.
Hendricks, J. S., Booth, T. E.
openaire   +1 more source

Development of a practical and high‐speed deep learning‐based dose calculation model in boron neutron capture therapy for head and neck cancer

Medical Physics, Volume 53, Issue 5, May 2026.
Abstract Background In boron neutron capture therapy (BNCT), Monte Carlo (MC) dose calculations are commonly employed because of the complicated neutron reactions. However, MC dose calculations are generally time‐consuming. Recently, deep learning (DL)‐based dose prediction/calculation has attracted increasing attention; however, the applications of DL
Ryohei Kato, Noriyuki Kadoya, Takahiro Kato, Akihiko Takeuchi, Shinya Komori, Keiichi Jingu, Yoshihiro Takai   +6 more
wiley   +1 more source

Alpha-like calculations with MCNP [PDF]

, 1997
Alpha (time-absorption eigenvalue) calculations are not an explicit calculational option in MCNP. Nevertheless, it is possible to perform alpha calculations with MCNP.
Parsons, D.K.
core  

Network‐wide assessment of soil water content calibration and sensitivity to biomass proxies using cosmic‐ray neutron sensing in the Roaring Fork Basin, Colorado

Vadose Zone Journal, Volume 25, Issue 3, May/June 2026.
Abstract Soil water content (SWC) is a key state variable of the climate system but is often uncertain in water balance monitoring, especially in alpine environments. SWC measurements can be challenging in alpine environments due to the topography and rocky soils.
Sophia M. Becker, Gwendolyn E. Davies, Trenton E. Franz, Tyler D. Lampard, Todd G. Caldwell   +4 more
wiley   +1 more source

Direct Growth of Transparent Boron Nitride Neutron Shielding Layer for Space Window

Advanced Science, Volume 13, Issue 20, 9 April 2026.
Direct growth of sp2‐sp3 hybridized BN (HBN) on quartz, enabled by an h‐BN buffer, produces transparent and stable films up to 80 µm thick with high transmittance and strong neutron shielding, making HBN a promising candidate for space windows in long‐term lunar missions.
Dobin Kim, Geunpil Kim, Hwijoon Jeong, Sk Mujaffar Hossain, Satadeep Bhattacharjee, Minjae Isaac Kwon, Yeunjeong Lee, Chanhee Yang, Yeong Seok Ham, Taek‐Soo Kim, Hyowon Moon, Inkyu Park, Seung‐Cheol Lee, Jinhwan Kim, Jongbum Kim, Jaehyun Park   +15 more
wiley   +1 more source

NJOY and MCNP

, 2016
This presentation shares exercises that utilize the NJOY input deck in 235 U material calculations.
openaire   +2 more sources

Re-characterization of two n-type planar HPGe detectors based on experiments and Monte Carlo modeling [PDF]

Ядерна фізика та енергетика
Accurate gamma-ray spectrometry using High Purity Germanium (HPGe) detectors relies on precise knowledge of detector efficiency, particularly the full energy peak efficiency (FEPE), which can degrade over extended periods of operation due to the growth ...
K. Abd El Gawad, M. H. Hazzaa
doaj   +1 more source

A multi-agent system for automated MCNP input review using open-weight LLMs

Nuclear Engineering and Technology
Large language models (LLMs) have demonstrated promising performance in code generation, but their reliability remains limited for domain-specific simulation codes, such as Monte Carlo N-Particle (MCNP), which requires a strict card-based syntax and ...
Byoungil Jeon, Soobin Lim
doaj   +1 more source