Physics Forums » Nuclear Engineering
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Join other experts in a discussion on nuclear engineering in the Physics Forum. Discuss topics on the design, construction, and operation of nuclear reactors. You can also talk about Radiation Protection, Radioactive Waste, Design, and Reactors as well! Meet nuclear engineers and learn more about nuclear reactions, equipment, and more.
Physics Forums » Nuclear Engineering
1w ago
Hello, I doing my thesis, I'm beginner in MCNPX. I want to ask about transformation in MCNPX, I want to transform this head phantom in inside and outside field ( radiation using LINAC from face to ear) in angle 90° and 270 °. Can anyone help me to solve this problem with transformation code ..read more
Physics Forums » Nuclear Engineering
1w ago
Good evening,
I am new to this forum and do not have a strong physics background. So if my questions seem woefully inept please respond with a simple laymans answer.
I understand that there are 2 basic ideas for fusion containment, and that the main 2 components of any successful fusion...
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Physics Forums » Nuclear Engineering
2w ago
Greetings and Regards
I had trouble getting the gamma results (719 KeV) by mcnpx 2.6 in the article below. Please guide me if possible. Thanks ..read more
Physics Forums » Nuclear Engineering
2w ago
Will SMR's (Small Modular Reactors) allow for nuclear powered surface combatants to make a comeback?
The US Navy used to operate a fleet of nuclear powered cruisers in addition to aircraft carriers and submarines. Most were based on the General Electric D2G reactor, which is around 30x30x40...
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Physics Forums » Nuclear Engineering
1M ago
Dear all,
I am a new user of MCNP, I have a problem declaring 2 sources F-18 and I-131 in 2 different cells. I only know how to declare each source for each cell, but when combining them into one declaration, I don't know how to do it. Here are my two source declarations. Please help me. Thank ..read more
Physics Forums » Nuclear Engineering
1M ago
Hello, every body, I'm a new gust in this forum , and I have a question to the users of the simulation VISED version of MCNP software.
Can we change some parameters in the materials part of the input file then reread the tally again to plot two different curves together on the same graph, or...
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Physics Forums » Nuclear Engineering
1M ago
I'm beginning in Vised for MCNP6 and i want to modify my imput file inside vised to understand how when i changed cards this affects the simulation. The problem is that i can't save inside vised my imput file, i have to open my imput file in an editor text an then reopen this file in vised...
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Physics Forums » Nuclear Engineering
1M ago
I'm dealing with a specific situation: I'm analyzing Linear Energy Transfer (LET) in a cylindrical sample. According to the definition of LET in the manual, we have:
“The linear energy transfer (LET) special tally option allows track length tallies to record flux as a function of stopping power...
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Physics Forums » Nuclear Engineering
1M ago
Hello,
I'm currently working on a project that studies the influence of a PE moderator on the neutron capture rate of a He3 detector. So far, I've only experimented with the thickness of the PE moderator. The results I have obtained are interesting and I'm trying to justify them. In order to do...
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Physics Forums » Nuclear Engineering
2M ago
I'm dealing with a specific situation: I'm analyzing Linear Energy Transfer (LET) in a cylindrical sample. According to the definition of LET in the manual, we have:
“The linear energy transfer (LET) special tally option allows track length tallies to record flux as a function of stopping power...
Read more ..read more