How Can I Find Real Accelerators for BNCT Data Comparison?

AI Thread Summary
The discussion centers on the search for real accelerator-based neutron sources for Boron Neutron Capture Therapy (BNCT) to compare with MCNP-X output data. The user is conducting research using a 2.5 MeV imaginary accelerator and seeks guidance on locating relevant theses or data. Suggestions include utilizing Google to search for resources related to Kyoto and BNCT. A specific link to a paper from the Cyclotrons 2010 conference is provided as a potential resource. The conversation highlights the challenge of finding applicable real-world data for BNCT research.
ms.shafeie
Messages
17
Reaction score
0
Hello All
I'm doing my theses in BNCT(Boron neutron capture therapy).I did it with 2.5 Mev imaginary accelerator.
there are many reactors to compare my data with theirs.but Unfortunately I couldn't find some Real accelerators based on BNCT to compare my MCNP-X output data with theirs.
could u please guide me.
How can I find them?
 
Engineering news on Phys.org

Thread 'MCNP6 BURN Card Issue: Zero Burnup for Material in Fuel Assembly'

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...
View full post »

Thread 'Beginner Seeking Help: MCNP6 Burnup Example (OECD-NEA Benchmark)'

Hi everyone, I'm a complete beginner with MCNP and trying to learn how to perform burnup calculations. Right now, I'm feeling a bit lost and not sure where to start. I found the OECD-NEA Burnup Credit Calculational Criticality Benchmark (Phase I-B) and was wondering if anyone has worked through this specific benchmark using MCNP6? If so, would you be willing to share your MCNP input file for it? Seeing an actual working example would be incredibly helpful for my learning. I'd be really...
View full post »

Similar threads

BNCT(Boron Neutron Capture Therapy)
Replies
4
Views
3K
Boron Neutron Capture Therapy (B10->B11)
Replies
18
Views
11K
Question about Resonance Cross Sections
Replies
2
Views
2K
MCNP Cylindrical Phantom Calculation Help
Replies
1
Views
4K
How to automate tests on a physical model without real data
Replies
4
Views
1K
I Can spallation be used as a controlled neutron source?
Replies
11
Views
3K
How do I calculate a "medium" jerk value of my motion data?
Replies
5
Views
3K
How can I make an experimental Nyquist plot using my data?
Replies
14
Views
8K
How to find transfer function of real world system?
Replies
11
Views
9K
How Can Plasma Be Created and Ignited in Toroidal Fusion Reactors?
Replies
4
Views
4K

Hot Threads

Recent Insights

Back
Top