Neutron transport equation and pressure drop calculations in core ...

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Discussion Overview

The discussion revolves around the neutron transport equation and pressure drop calculations in nuclear reactor cores. Participants seek to understand fundamental concepts related to neutron behavior in reactors and fluid mechanics as it pertains to reactor design and operation.

Discussion Character

  • Exploratory
  • Technical explanation
  • Homework-related

Main Points Raised

  • Some participants express a need for foundational understanding of the neutron transport equation and its relevance in reactor theory.
  • There is mention of the importance of delayed neutrons in controlling reactor operations during the withdrawal of control rods.
  • Fluid mechanics is described as crucial for understanding how fluids behave in reactor cores, particularly regarding pressure and temperature effects on heat transfer mechanisms.
  • One participant indicates difficulty in grasping fluid mechanics concepts due to a mixed background in their class, which includes both mechanical engineers and scientists.
  • A specific request is made for assistance with pressure drop calculations, particularly the differences between calculating pressure drop across a single fuel rod versus the entire core, referencing a specific textbook.

Areas of Agreement / Disagreement

Participants generally agree on the significance of both neutron transport and fluid mechanics in nuclear engineering, but the discussion remains unresolved regarding specific calculation methods and conceptual understanding.

Contextual Notes

Participants express varying levels of familiarity with the topics, indicating a potential gap in foundational knowledge that may affect their ability to solve related problems.

Who May Find This Useful

Students and professionals in nuclear engineering, particularly those interested in reactor theory and fluid mechanics, may find this discussion relevant.

sehrish shakir
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i am a physicist now i am doing Ms in nuclear engineering ... i need to understand basic concepts ...
neutron transport equation ? what is the transport phenomenon actually ?
and pressure drop calculations in core ... please help thanks in advance
 
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sehrish shakir said:
i am a physicist now i am doing Ms in nuclear engineering ... i need to understand basic concepts ...
neutron transport equation ? what is the transport phenomenon actually ?
and pressure drop calculations in core ... please help thanks in advance
Those are two broad areas. I would imagine that one will take courses in reactor theory and fluid mechanics in which one would learn both subjects.

A fission reaction releases 2 or 3 neutrons in addition to the two fission product radionuclides and gamma radiation. Some fission products also release neutrons, and that population is called 'delayed neutrons' which allow for control of the reactor during withdrawal of control rods. Fission neutrons are born with energies in the low MeV range, and they must be slowed or 'moderated' to less the 0.1 eV, or 7-8 orders of magnitude in energy to increase the probability of causing additional fissions. Transport theory and its approximation, diffusion theory, addresses how a population of neutrons behave in a reactor environment.

Fluid mechanics describes how fluids behave when flowing through structures such as pipes, or in the case of a reactor, through the core. The fuel assemblies impose a resistance, or drag, on the coolant. The pressure, in conjunction with temperature, is important as it influences the heat transfer mechanism, forced convection, and it is important in pressurized water reactors (PWRs) to limit nucleate boiling toward the top of the core (the coolant condition must remain below the point of departure from nuclear boiling, DNB), whereas in boiling water reactors (BWRs) must remain below a critical power at which boiling transition, or dryout, occurs.
 
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Astronuc said:
Those are two broad areas. I would imagine that one will take courses in reactor theory and fluid mechanics in which one would learn both subjects.

A fission reaction releases 2 or 3 neutrons in addition to the two fission product radionuclides and gamma radiation. Some fission products also release neutrons, and that population is called 'delayed neutrons' which allow for control of the reactor during withdrawal of control rods. Fission neutrons are born with energies in the low MeV range, and they must be slowed or 'moderated' to less the 0.1 eV, or 7-8 orders of magnitude in energy to increase the probability of causing additional fissions. Transport theory and its approximation, diffusion theory, addresses how a population of neutrons behave in a reactor environment.

Fluid mechanics describes how fluids behave when flowing through structures such as pipes, or in the case of a reactor, through the core. The fuel assemblies impose a resistance, or drag, on the coolant. The pressure, in conjunction with temperature, is important as it influences the heat transfer mechanism, forced convection, and it is important in pressurized water reactors (PWRs) to limit nucleate boiling toward the top of the core (the coolant condition must remain below the point of departure from nuclear boiling, DNB), whereas in boiling water reactors (BWRs) must remain below a critical power at which boiling transition, or dryout, occurs.
thank you very much i have taken a course on fluid mechanics but i think i was unable to understand it well ... as our class consists of mechanical engg as well as scientists so the very basic knowledge was not provided so i was unable to handle problems in paper ... i need to understand the deep concepts and how to solve the given problems ... i am studying reactor theory courses in this semester hopefully i will be able to understand the concept very well ...
 
Respectable @Astronuc
thank you for the kind response sir,
please if you can provide help regarding pressure drop calculation mentioned in kazmi book ?
question is what is the main difference in calculating the pressure drop across one fuel rod and entire core .
chap #9 single phased fluid mechanics ...
provide any link regarding calculations your help would be appreciated ...
 

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