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

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22.091 Nuclear Reactor Safety

Spring 200 8

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