Results 111 to 120 of about 8,745 (215)

Fusion Based Neutron Sources for Security Applications: Energy Optimisation [PDF]

, 2014
There is a growing interest in the use of neutrons for na- tional security. The majority of work on security focuses on the use of either sealed tube DT fusors or fission sources, e.g. Cf-252.
Seviour, Rebecca, Albright, S.
core  

Status of electron transport in MCNP{trademark}

, 1995
In recent years, an ongoing project within the radiation transport group (XTM) at Los Alamos National Laboratory has been the implementation and validation of an electron transport capability in the Monte Carlo code NICNP.
Hughes, H.G.
core  

Monte Carlo simulations of 241 Am α -particle energy distribution, LET distribution, and absorbed dose in a cell layer. [PDF]

Med Phys
Araszkiewicz M, Tymińska K, Kaźmierczak U, Chuchała P, Grzyb J, Kamińska P, Kwiatkowski R, Maleszewska M, Malinowska A, Maliszewska-Olejniczak K, Paterczyk B, Korgul A.   +11 more
europepmc   +1 more source

MCNP application for the 21 century

, 2000
The Los Alamos National Laboratory (LANL) Monte Carlo N-Particle radiation transport code, MCNP, has become an international standard for a wide spectrum of neutron, photon, and electron radiation transport applications.
McKinney, M.C.
core  

Nuclear archaeology reassesses Heisenberg's last reactor experiment. [PDF]

PNAS Nexus
Park PJ, Robertson B, Hiebert ME, Zhao J, Sivels CB, Koeth TW.   +5 more
europepmc   +1 more source

MCNP User Manual : Code Version 6.2

, 2018
Buku ini berisi manual penggunaan dan teori MCNP terkini dan historis.x, 732 ...
Werner, Christopher J
core  

Radiation shielding and hydro-mechanical performance of bentonite-copper slag mixtures. [PDF]

Sci Rep
Nasiri F, Rowshanzamir MA, Isfahani HS, Hejazi SM, Marri S.   +4 more
europepmc   +1 more source

Synthesis and evaluating gamma shielding features of YBa₂Cu₃O₇(Bi₂O₃) ceramic composite using Monte Carlo method via GEANT4 and MCNP codes. [PDF]

Sci Rep
Soltani E, Saray AA.
europepmc   +1 more source

MCODE, Version 2.2: An MCNP-ORIGEN DEpletion Program

, 2008
MCODE Version 2.2 is a linkage program, which combines the continuous-energy Monte Carlo code, MCNP-4C, and the one-group depletion code, ORIGEN2, to perform burnup calculations for nuclear fission reactor systems. MCNP is used as the advanced physics
Hejzlar, Pavel, Xu, Z.
core  

A novel 3D visualization method in mice identifies the periportal lamellar complex (PLC) as a key regulator of hepatic ductal and neuronal branching morphogenesis. [PDF]

Elife
Xu T, Cao F, Zhou R, Chen Q, Zhong J, Wang Y, Xiao C, Yin B, Chen C, Zhao C.   +9 more
europepmc   +1 more source