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Systems Analysis of the Nuclear Fuel Cycle >> Content Detail



Labs



Labs



Lab Resources


Appendix A (PDF)



Labs



LEC #TOPICSSOLUTIONS
1

Assignment (PDF)

CASMO-4 Introduction (PDF)

CASMO-4 Fuel Composition Input Description, pages 3-36 and 3-37 of the CASMO-4 User's Manuel

(PDF)
2

Assignment (PDF)

Croff, Allen G. "ORIGEN2: A Versatile Computer code for Calculating the Nuclide Compositions and Characteristics of Nuclear Materials." Nuclear Technology 62 (1983): 335 - 352.

ORIGEN 2.1 Introduction (PDF)

(PDF)
3

Assignment (PDF)

(PDF)
4

Presentation (PDF) (Courtesy of Pavel Hejzlar. Used with permission.)

Assignment (PDF)

(PDF)
5

Presentation (PDF) (Courtesy of Pavel Hejzlar. Used with permission.)

Assignment (PDF)

(PDF)
6

Presentation (PDF) (Courtesy of Pavel Hejzlar. Used with permission.)

Assignment (PDF)

VIPRE 01 - Thermal Hydraulic Code for Reactor, User's Manual Vol. II, Revision 3

(PDF)

 








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