Search found 135 matches

by Peter Wolniewicz
Mon Jan 30, 2017 2:51 pm
Forum: Gamma transport
Topic: Gamma detectors and flux to dose
Replies: 37
Views: 12596

Re: Gamma detectors and flux to dose

See the reference at: http://serpent.vtt.fi/mediawiki/index.php/ENDF_reaction_MT's_and_macroscopic_reaction_numbers The units are in Gy, normalization depends on how the source is normalized. Okay thanks.. A.) If I have a body composed of different radioactive nuclides and multiple cells, and where...
by Peter Wolniewicz
Mon Jan 30, 2017 12:58 pm
Forum: Gamma transport
Topic: Gamma detectors and flux to dose
Replies: 37
Views: 12596

Re: Gamma detectors and flux to dose

Using
dr -203 (photon dose in air, Dry (Near Sea Level))

on a detector volume,

What is the unit in the detector output and what is it normalized to?
by Peter Wolniewicz
Mon Jan 30, 2017 11:24 am
Forum: Input
Topic: Restart feature in 2.1.17
Replies: 29
Views: 37617

Re: Restart feature in 2.1.17

Jaakko Leppänen wrote:Which code version are you using?
Jaakko:

2.1.26
by Peter Wolniewicz
Thu Jan 26, 2017 4:41 pm
Forum: Gamma transport
Topic: Photon detectors
Replies: 6
Views: 4408

Re: Photon detectors

Is there a way to get a pulse tally just like F8 (I think it is) in MCNP?

Lets say I put some radioactive material in my simulation and construct a germanium detector in which I tally "pulses" :)

best regards,
Peter
by Peter Wolniewicz
Thu Jan 26, 2017 3:14 pm
Forum: Input
Topic: Restart feature in 2.1.17
Replies: 29
Views: 37617

Re: Restart feature in 2.1.17

I compiled it in debug mode and I got the same result in terminal: SUMMARY -- 91 nuclides included in calculation: - 91 elements with photon interaction data - Photon energy cut-offs at 1.00E-03 and 100.0 MeV - 364 transport reactions - 91 special reactions - 95.13 Mb of memory allocated for data No...
by Peter Wolniewicz
Thu Jan 26, 2017 3:10 pm
Forum: Input
Topic: Restart feature in 2.1.17
Replies: 29
Views: 37617

Re: Restart feature in 2.1.17

The geometry doesn't have to be, but the material names must match. In any case you shouldn't get a segfault. Could you try running the calculation in debug mode? To run it in debug mode, do I uncomment the debug flag in the Makefile: #CFLAGS += -DDEBUG make clean make all and then just run the exe...
by Peter Wolniewicz
Thu Jan 26, 2017 1:46 pm
Forum: Input
Topic: Restart feature in 2.1.17
Replies: 29
Views: 37617

Re: Restart feature in 2.1.17

Hi!

Must the geometry be the same using the restart feature? I have an activated material and I want to put it in a different geometry and using the restart feature.

I tried, but I get segmentation fault:

Reading material compositions from restart file...
Segmentation fault (core dumped)
by Peter Wolniewicz
Thu Jan 26, 2017 1:09 pm
Forum: Gamma transport
Topic: Radioactive decay source
Replies: 14
Views: 6923

Re: Radioactive decay source

The problem is more generally related to using natural element compositions in burnable (activated) materials. When you run the neutron transport calculation, Serpent doesn't know what to do with nuclides such as 16000.03c. This is not really the main cause of this error, but replacing the elementa...
by Peter Wolniewicz
Wed Jan 25, 2017 10:34 pm
Forum: Input
Topic: Increasing scores in optically thin materials
Replies: 4
Views: 7071

Re: Increasing scores in optically thin materials

Thanks ill try that
by Peter Wolniewicz
Wed Jan 25, 2017 5:22 pm
Forum: Users
Topic: burnup -> use as source
Replies: 3
Views: 1826

burnup -> use as source

Hi! 1.) As I understand I must specify all constituting nuclides in a material in a burnup calculation to be using the same ending (e.g., .70c) or I get the following error: Fatal error in function BurnMatCompositions: No S(a,b) flags? Simulation aborted. 2.) If I later use the bumat material create...