MCNP 5 User Guide: Detailed Documentation & Authorization Info

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MCNP is a restricted technology due to its potential applications in nuclear design calculations, which require authorization for access to certain documentation, such as that from LANL. The code is utilized in various fields, including medical physics, accelerator-driven energy sources, and radiation protection. Current applications also encompass neutron scattering, nuclear waste transmutation, and charged-particle propulsion concepts. For those seeking additional resources, links to MCNP manuals and documentation are available. Accessing comprehensive information can enhance understanding and application of MCNP in academic and research settings.
theCandyman
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I have to write some input for MCNP for one of my classes. The graduate student had given us a lecture and some examples, but I'm trying to find some more detailed documentation, but even anything basic would be nice.

The one I did run across, from LANL, I needed authorization to view, why is that?
 
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MCNP is restricted technology because it could be used to certain types of nuclear design calculations.

Current applications for the code include among others:
Design of accelerator spallation targets, particularly for neutron scattering facilities; Investigations for accelerator isotope production and destruction programs, including the transmutation of nuclear waste; Research into accelerator-driven energy sources; Medical physics, especially proton and neutron therapy; Investigations of cosmic-ray radiation backgrounds and shielding for high altitude aircraft and spacecraft ; Accelerator-based imaging technology such as neutron and proton radiography; Design of shielding in accelerator facilities; Activation of accelerator components and surrounding groundwater and air; Investigation of fully coupled neutron and charged-particle transport for lower energy applications; High-energy dosimetry and neutron detection; Design of neutrino experiments; Comparison of physics-based and table-based data; Charged-particle tracking in plasmas; Charged-particle propulsion concepts for spaceflight; Single-event upset in semiconductors, from cosmic rays in spacecraft or from the neutron component on the Earth's surface; Detection technology using charged particles (i.e., abandoned landmines); Nuclear safeguards; Nuclear criticality safety; Radiation protection and shielding; Oil well logging.
http://www.nea.fr/abs/html/ccc-0730.html
 
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We are collecting http://mcnpx.net/mcnp-manual-mcnpx-manual".
If you need one, than have a look on what we have found.
theCandyman said:
I have to write some input for MCNP for one of my classes. The graduate student had given us a lecture and some examples, but I'm trying to find some more detailed documentation, but even anything basic would be nice.

The one I did run across, from LANL, I needed authorization to view, why is that?
 
Last edited by a moderator:
Hello, I'm currently trying to compare theoretical results with an MCNP simulation. I'm using two discrete sets of data, intensity (probability) and linear attenuation coefficient, both functions of energy, to produce an attenuated energy spectrum after x-rays have passed through a thin layer of lead. I've been running through the calculations and I'm getting a higher average attenuated energy (~74 keV) than initial average energy (~33 keV). My guess is I'm doing something wrong somewhere...

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