Lesson 2 Objectives - PowerPoint PPT Presentation

1 / 23
About This Presentation
Title:

Lesson 2 Objectives

Description:

Same spatial (finite difference) and energy (multigroup) treatments as transport theory ' ... Diffusion Theory (2) Of more importance to us are assumptions: ... – PowerPoint PPT presentation

Number of Views:38
Avg rating:3.0/5.0
Slides: 24
Provided by: ronald55
Category:

less

Transcript and Presenter's Notes

Title: Lesson 2 Objectives


1
Lesson 2 Objectives
  • Fission chain reactor
  • 4 factor formula
  • Time dependence concepts
  • Diffusion concepts

2
Chapter 2 Neutron Chain Fission Reactors
  • Mainly 4 factor formula. Keep these straight

3
Integral form of 4-factor formula
4
Time dependence
  • Introduce N0 neutrons at time0
  • Solve it for N(t) at 100 lifetimes with S0,
    k1.005

5
Steady-state with constant source
  • Source multiplication
  • Basis for 1/M method of reactor startup

6
Effect of delayed neutrons
7
Effect of delayed neutrons (2)
  • Note similarity to source equation except
  • (k-1) replaced with (k-b-1)
  • k vs. 1b is measure of prompt criticality
  • Precursor concentration rises (slowly) with time

8
Prompt-jump (-drop) approximation
  • The prompt jump and drop assume that the
    neutron flux will instantly respond to k(t) at
    the current source level of C(t). Set the
    neutron derivative to 0
  • Substitute into C(t) equation
  • This exponential sets the pace for power rise
    (or fall)

9
Diffusion Theory
  • Diffusion theory Simplified treatment of
    direction components of neutron flux
  • Same spatial (finite difference) and energy
    (multigroup) treatments as transport theory
  • One speed Multiple groups coupled through
    scattering and fission

10
Diffusion Theory (2)
  • Of more importance to us are assumptions
  • Uniform medium
  • Isotropic scattering
  • Slowly varying flux
  • Absorption small compared to scattering
  • No sources nearby
  • Results Ficks law
  • General reasonableness of Ficks Law?

11
Derivation of Diffusion Theory from Transport
Theory

12
Derivation of Diffusion Theory from Transport
Theory (2)

13
Derivation of Diffusion Theory from Transport
Theory (3)
  • Resulting equation for L1
  • Form the kth flux moment equations

14
Derivation of Diffusion Theory from Transport
Theory (4)
  • If we set , we get the coupled
    equations
  • or

15
Derivation of Diffusion Theory from Transport
Theory (5)
  • If we define the absorption cross section as
  • And the diffusion coefficient as
  • This becomes

16
Interface and Bound. Cond.s
  • Partial currents
  • Interface conditions
  • Boundary conditions
  • Reflected

17
Vacuum Boundary Conditions
  • Rigorous
  • Can use directly (mixed)
  • Can convert to an approximate extrapolated
    0-flux
  • Can ignore the extrapolation

18
One-Speed Diffusion Equation
  • The diffusion equation in 3D is
  • Questions
  • What is the meaning of the vector operators?
  • Where is scattering? What order is it?
  • Why was fission separated out?
  • What are the limitations on the source?
  • Inside a homogeneous region

19
Applicability of Diff. Theory
  • Return to the assumptions
  • Uniform medium
  • Isotropic scattering
  • Slowly varying flux
  • Absorption small compared to scattering
  • No sources nearby
  • How can we apply it to a reactor?

20
Diffusion migration lengths
  • LDiffusion length
  • L21/6 mean squared distance traveled by thermal
    neutron to captureD/Sa
  • tage to thermal1/6 mean squared distance
    traveled by fast neutron to thermal
  • Mmigration length
  • 1/6 mean distance squared
    traveled by a
  • neutron from birth to
    absorption
  • Table 3.1 and the kernels of Equation 3.26

21
Homework 2
  • Assume you have a critical reactor with
  • At t0, the k instantaneously jumps to 10 cents
    supercritical (k10.1b)
  • What will be the time behaviour of N(t), assuming
    the prompt-jump approximation?
  • Check the PJ approximation What is the
    approximate time that it took for the neutron
    population to make 99 of the jump?

22
Homework 2 (contd)
  • Work problems 2.1 and 3.4 from the text
  • Give a complete derivation of diffusion theory
    from transport theory (Slides 11-15) by including
    the integrations I skipped
  • Add a column to Table 3.1 for the mean distance
    traveled by a neutron
  • From birth to thermalization
  • From thermalization to absorption
  • Total (from birth to absorption)

23
Homework 2 (contd)
  • Using the point kernel for the flux (Eq. 3.26)
    and remembering that
  • Absorption profile is flux time absorption
    cross-section
  • dV4pr2dr for a sphere about a point
  • Show that L squared is 1/6 of average distance
    travelled from birth (at origin) to absorption
    squared, i.e.,
  • What is the average distance travelled from birth
    to absorption (in terms of L)?
Write a Comment
User Comments (0)
About PowerShow.com