Operational Reactor Safety

22.091 /22.903

Professor Andrew C. Kadak Professor of the Practice

Lecture 4

Fuel Depletion & Related Effects

Topics to Be Covered

Fuel “burnup”

Transmutation

Conversion/Breeding

Samarium 149

Xenon 135

Operational Impacts

Fuel Burnup

Depletion Equation

Definition of burnup

t hermal energy output per mass of fuel

M WD/MTHM

Transmutation

Equation for production of any nuclide

Conversion versus Breeding

Depending on core physics design of the reactor core

Ș (eta)

Number of neutrons produced/absorbed in fuel

Conversion ratio

r ate of creation of new fissile/destruction of existing fissile

Breeding Ratios for Reactor Systems

Buildup of Plutonium with Burnup

http://atom.kaeri.re.kr/

Reactivity Penalty

Fission Products

Fission Fragments Fission Products

R ate of Creation - Ȗ Ȉ f ĭ

Ȗ fission yield

Fission Fragment Balance Equation

Department of Nuclea r S c ien ce & Engineering

Prof. Andrew C. Kadak, 2008 Page 10

Samarium Buildup

Samarium Buildup

Xenon Buildup

Fuel Depletion and Related EJerl/ 17 J

0.6

0.5

P O l S O N h l lG, bklk

0.4

0.3

0.2

0.1

0 10 D 0 40 50 60 70

TIME AFTER SHUTDOWN, h

FIGURE 6-8

Poisoning of "'Xe as a function of tims afler shutdown for a repre<nutive LWR fuel composition at vaHous neutron flux levels. Curve 1: & = 1 x 10" n/cm 2 s; Cuwc 2: & = 5 X 10'° n/cm’-s; Curve 3: & = 1 x l0 ' 4 n/cm 2 - s; Curve 4: & = 5 x 10'° n/cm'-s.

Operational Impacts

X enon Oscillations

F uel Design for cycle length of core

F uel management strategies

P ower peaking limits

P ower distribution control

Reactor Physics Calculations

M ulti-Group Diffusion Equations

M odel core u sing fuel pin and assembly homogenization of materials and fuels with pins averaged horizontally but detailed axially

R un Static calculation for core power and flux distribution

F luxes used to perform depletion calculations as noted for a “time step”

N ew material calculations used to produce new power and flux distribution for next “time step” 1 month

I ncorporate only significant isotopes h igh absorption and/or fission cross sections ignoring short liv ed isotopes in decay chains. u se lumping procedure

N eed to consider early xenon and Samarium build up 50 hours/500 hours

T rack key isotopes for all fuel assemblies for refueling management

Homework Assignment

Chapter 6

P roblems: 6.2, 6, 7, 9, 11, 15

Department of Nuclea r S c ien ce & Engineering

Prof. Andrew C. Kadak, 2008 Page 18

MIT OpenCourseWare http://ocw.mit.edu

22.091 Nuclear Reactor Safety

Spring 200 8

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