Aerospace Nuclear Science and Technology

AI Thread Summary
The Aerospace Nuclear Science and Technology Technical Group (ANS) aims to advance nuclear science and technology for aerospace applications. It focuses on developing nuclear power and propulsion systems, multifunctional materials for radiation protection, and safety strategies for non-specialized personnel operating nuclear systems. The group seeks to enhance aerospace design and operations, particularly for exploring planetary bodies and improving high-speed air travel safety. There is a push to innovate beyond previous projects, like Project Pluto, with an emphasis on concepts such as nuclear fusion rockets. The recent naming of NASA's crew exploration vehicle as "Orion" adds a layer of complexity to the discussions within the field.
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Aerospace Nuclear Science and Technology Technical Group (ANS)
http://anst.ans.org/

Please check it out. If you're a Nuclear Engineer, please get involved in ANS and ANST, if you're not already.

Mission:
To promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application.

Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel.

Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
 
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Trying to move beyond Project Pluto finally.
 
**cough** nuclear fusion rockets **cough**

Cool though...
 
This is going to get confusing, now that NASA has named the CEV "Orion".
 
Hello everyone, I am currently working on a burnup calculation for a fuel assembly with repeated geometric structures using MCNP6. I have defined two materials (Material 1 and Material 2) which are actually the same material but located in different positions. However, after running the calculation with the BURN card, I am encountering an issue where all burnup information(power fraction(Initial input is 1,but output file is 0), burnup, mass, etc.) for Material 2 is zero, while Material 1...
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