Liquid Scintillation Counter w/ fast neutron detectin isotop

AI Thread Summary
The discussion centers on detecting fast neutrons using a liquid scintillator cocktail with U-238 and a Cf-252 source. The user seeks guidance on calculating the wavelength of light emitted from the scintillator, light collection efficiency, and the number of photoelectrons reaching the photocathode. Expected emissions from the scintillator are around 350 nm. The setup includes a 1.5-inch diameter vial of scintillator connected to a photomultiplier tube, with access to necessary equipment like a PMT, oscilloscope, and counter/timer. Accurate calculations and measurements are crucial for effective neutron detection.
Priyo
Messages
6
Reaction score
0
I'm trying to make a LSC with U-238 (non-aqueous form) dipped in the scintillating cocktail to detect fast neutrons (no thermals or epithermals, only fast) from a Cf-252 source. How do I calculate the wavelength emerging from the cocktail (assuming U-238 does not react with the cocktail)? Also, how do I calculate the light collection efficiency, and the number of photoelectrons hitting the photocathode?

All the help that I can get, much much appreciated!
 
Engineering news on Phys.org
Does one know the expect emissions from the scintillator?

Does one have a spectrometer or access to one?

What is the geometry of the source with respect to the scintillator, and of the scintillator to the PM detector?
 
Thanks for your reply!

The expect emissions are about 350 nm wavelength.

I have access to The PMT, oscilloscope, counter/timer.

The source is Cf-252, in a reactor beam port, and the scintillator is a 1.5 in X 1.5 in diameter vial, attached with optical grease to a photo multiplier tube.
 

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

A Liquid Scintillation Counter using U-238 to detect neutrons
Replies
1
Views
2K

Hot Threads

Recent Insights

Back
Top