Recent content by mark_bose
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Assistance Needed with OpenMC to Calculate Air Kerma and Mean Glandular Dose for Breast Voxel Phantom
The creation of the mesh is done in two steps: first you create the mesh itself than you create the mesh filter using the MeshFilter function. OpenMC offers various options for the mesh (RegularMesh, CylindricalMesh...). For example here you can find the function for cylindrical mesh. It needs...- mark_bose
- Post #4
- Forum: Nuclear Engineering
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Assistance Needed with OpenMC to Calculate Air Kerma and Mean Glandular Dose for Breast Voxel Phantom
Hello, Could you add more details? what have you done up to now? Have you created the geometry and the source?- mark_bose
- Post #2
- Forum: Nuclear Engineering
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When does nuclear thermal propulsion outperform chemical propulsion?
It's true that, if we compare NTP and NEP reactor systems (at the same power), the latter would be heavier for the reason you mentioned. However, Isp in NEP is much higher than in NTP, shouldn't this allow to use less propellant and compensate for the heavier power system? Moreover, as far as...- mark_bose
- Post #9
- Forum: Aerospace Engineering
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When does nuclear thermal propulsion outperform chemical propulsion?
Thanks for your replies, I still have some doubts If that was the only reason then why don't we go directly with nucelar electric instead of complicate things with NTP? Isp is much larger. I'm not really an expert on this, but I imagine that provided we have sufficient propellant with chemical...- mark_bose
- Post #7
- Forum: Aerospace Engineering
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When does nuclear thermal propulsion outperform chemical propulsion?
Dear aerospace guys, From time to time, I think about nuclear thermal propulsion. As a nuclear enthusiast, I'd love to see nuclear reactors in space. Regarding Nuclear Thermal Propulsion (NTP), I understand that it theoretically offers a higher specific impulse compared to chemical propulsion...- mark_bose
- Thread
- Nuclear Rocket propulsion Space exploration
- Replies: 10
- Forum: Aerospace Engineering
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Calculating the coefficient of thermal expansion from density
Yes, it was a typo in the post (btw, thanks @Lord Jestocost for pointing that out). However, I wrote it correctly in the python script: import numpy as np import matplotlib.pyplot as plt #INL correlation for density rho_umo = lambda T: 17.15 - 8.63e-4 * (T + 20) #Theroetical derivation...- mark_bose
- Post #11
- Forum: Materials and Chemical Engineering
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Calculating the coefficient of thermal expansion from density
Isn't it the mean value theroem (Wikipedia)? By definition, the average value of a function ##f(x) ## in the range ##(a,b)## is ##\bar f = \frac{1}{b-a}\int_a^bf(x)dx##, consequently: $$\int_a^b f(x)dx = \bar f (b-a)$$- mark_bose
- Post #8
- Forum: Materials and Chemical Engineering
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Calculating the coefficient of thermal expansion from density
##\bar \alpha## is function of the integration extremes ##T_1## and ##T_0##. While ##T_0## is usually taken as environmental temperature, ##T_1## can be arbitrary selected. The meaning of ##\bar \alpha## is the "average CLTE" in the range ##(T_0,T_1)##, its value varies if the extremes vary as...- mark_bose
- Post #6
- Forum: Materials and Chemical Engineering
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Calculating the coefficient of thermal expansion from density
Thanks for your answer. You are right, it is a first order approximation, but I do not think that this is the problem: If so, the first order approximation and the INL correlation should at least agree at low ##\Delta T## but it is not the case. However, to be sure I can derive the real...- mark_bose
- Post #3
- Forum: Materials and Chemical Engineering
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Calculating the coefficient of thermal expansion from density
Hi all, I am trying to derive a relation (as function of temperature) for the coefficient of linear thermal expansion (CLTE) strating from a correlation for the density. But I'm getting a huge discrepancy from the experimental data. I'll start telling you some reasoning I did to get a relation...- mark_bose
- Thread
- Density Modeling Thermal expansion Uranium
- Replies: 11
- Forum: Materials and Chemical Engineering
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Searching for a single and complete resource about nuclear fuels
First of all thank you for the help. All the resources you linked seem very interesting. I was looking for the resources mentioned by @Astronuc and i found this interactive database from IAEA called THERMPRO (maybe it is linked to the THERSYST document?)...- mark_bose
- Post #7
- Forum: Nuclear Engineering
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Searching for a single and complete resource about nuclear fuels
Hello, I am looking for a comprehensive resource (paper, book or any kind of document) that contains the most relevant properties of most nuclear fuels. To be more specific, the information i am looking for are thermophysical properties, chemical compatibility with other materials and...- mark_bose
- Thread
- Complete Nuclear Nuclear fuel Resource Uranium
- Replies: 8
- Forum: Nuclear Engineering
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How to explain the effect of temperature profile on feedback coefficient?
I'm using Serpent and the assumption of @rpp about the procedure is correct. For what concern temperature profiles I'm using an exact proportionality with power in each ring of the core (labeled as "B" "C" "D" ...). Initial and final T. profiles are taken starting from power distribution and...- mark_bose
- Post #4
- Forum: Nuclear Engineering
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How to explain the effect of temperature profile on feedback coefficient?
Hi all, I'm trying to derive fuel temperature coefficient in a TRIGA reactor using a monte carlo code. When i do that, if i assume a radial temperature profile along the core, i obtain smaller value (-7pcm/K) than the one achieved with uniform temperature (-9pcm/K). More in detail: in my case...- mark_bose
- Thread
- Coefficient Explain Feedback Temperature
- Replies: 4
- Forum: Nuclear Engineering
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I want to write my own Monte Carlo code for Neutron transport
Thank you all for the suggestions. Probably i will start with the simplifications you suggest. It seems that "Theory and Methodology" chapter in OpenMC manual could be useful.- mark_bose
- Post #10
- Forum: Nuclear Engineering