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NucE 430 Design Principles of Reactor Systems
Course
Description
This course covers nuclear power
cycles; heat removal problems; kinetic behavior of nuclear systems; material
and structural design problems; including the following course objectives:
 | Understand the design of
Nuclear Power Reactor, how they work and why, |
 | Understand and apply
design criteria which determine the power level and system efficiency in
power reactor cores, |
 | Become familiar with and
understand appropriate power reactor terminology and use, |
 | Learn how to perform
thermal/hydraulic calculations for different reactor designs, |
 | Learn the different accident
classifications and reactor operating limits. |
Topics covered include:
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Light water and
breeder reactor cycles
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Practical cycles
for light water reactors
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Reactor heat
generation
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Analysis of the
interplay of core and plant temperatures
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Hot channel
factors
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Heat transfer to
boiling liquids
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Calculation of
heat transfer coefficients for an LWR
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Preliminary core
thermal design
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Nuclear accidents
Current Course
Offering Schedule via C&DE
Semester: Fall
2009
Day and Time: TBA
Location: TBA
Start Date:
August 24, 2009
End Date:
December 18, 2009
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Resident students are
required to attend the live lectures in Room 308 Hammond Building.
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Distance students can
receive the class lectures via:
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interactive live video
conferencing |
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live streaming audio/video
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on-demand streaming
audio/video |
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mailed VHS tape or DVD as
needed |
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Course Instructor:
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Dr. Lawrence Hochreiter
Professor of Mechanical & Nuclear Engineering
The Pennsylvania State University
233 Reber Building
University Park, PA 16802
Phone: 814-865-6198
Fax: 814-865-8499
email:
lehnuc@engr.psu.edu |
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PSU Course Catalog Description
NUC E 430 Design Principles of Reactor Systems (3) Nuclear power
cycles; heat removal problems; kinetic behavior of nuclear systems; material
and structural design problems.
Prerequisite:
M E 410;
NUC E 301 or
NUC E 401
No Required Course Textbook:
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Instructors
Class Notes and Handouts will be posted in ANGEL |
Reference texts:
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Nuclear Heat Transport,
M.M. El Wakil, American Nuclear Society, 1978 |
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Thermal Analysis of Pressurized Water Reactors, L. Tong and J.
Weisman, American Nuclear Society, 1978 |
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The enrollment process is:
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Contact the the Office of Continuing and Distance Education for
admission into the course at 814-865-7643.
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Complete and submit the Registration Form via mail,
fax, or in person. See the Registration Page.
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Important Dates for
Current Offering
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First day of instruction |
August 24, 2009 |
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End of course |
December 18, 2009 |
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