NUCE 431W 

 

 

NucE 431W – Synthesis of Nuclear Systems

 

 

 

INSTRUCTORS

 

Dr. K. N. Ivanov                                                                      Dr. L. E. Hochreiter

206 Reber Building                                                                   233 Reber Building

kni1@psu.edu                                                                          lehnuc@engr.psu.edu

Phone: 865-0040                                                                     Phone: 865-6198

 

TEXTBOOKS

 

1)      K. Ivanov and L.E. Hochreiter NucE 431W Class Notes, PSU, 2006

 

 

2)      J. Duderstadt and L. Hamilton, “Nuclear Reactor Analysis” – Chapters 11, 12, 13, 14 and 15

.

3)      Westinghouse Computer Codes Theory and Input Manuals.

 

4)   Recommend, not required, “The Nuclear fuel Cycle:, Analysis and Management” by R.G. Cochran and N.Tsoulfanidis, 2nd edition, ANS 1999. (We will provide chapters 4 and 6 for the class.)

 

 

COURSE OUTLINE            

 

      Introduction to the course, course objectives

Grading, homework, projects, Westinghouse involvement

Attendance

Extra credit for Seminars

Introduction to Reactor Core Design

 

      Introduction to Reactor Core Design Con’t

Basic design parameters

 

Methods for Reactor Core Design and Iteration between neutronics and heat transport calculations

 

BWR core reload methodology

 

      Two group diffusion theory for reactor core analysis

 

      Reactor Fuel Design and Fabrication

                              C&T text chapter 4

 

PWR and BWR Core Limits and Operating Space

 

            Generating group constants for the core calculations

 

      Advanced homogenization techniques

 

      Refueling Activities and Reload Core Design Process

                              C&T text – section 6.5 and Westinghouse Notes

 

      Computer locations and UNIX input

 

      Meeting 1 with Westinghouse on nuclear design codes

 

Core models

Input and Output requirements – visualization features

Definition and discussion of the team design projects     

 

      Cross-section functionalization

                             

      Fuel loading patterns and loading pattern methodology

                              C&T text – sections 6.1-6.3 and Westinghouse Notes

 

      Meeting 2 with Westinghouse on designing core loading pattern

 

      Features of advanced assembly spectrum/depletion codes:

 

·    Physics models

·    Geometry options and basic libraries

·    Applications – depletion and branch calculations

·    Input and output

 

      Methods for evaluating of reactor power distribution

 

      Multi-dimensional neutron physics models:

 

·    Two-group nodal diffusion model

·    Geometry and boundary conditions

·    Baffle/reflector representation

·    Pin power reconstruction

·    Approaches for fuel depletion analysis

 

      Core design and excess reactivity requirements

 

      Equilibrium Xenon and Samarium calculations

 

Meeting 3 with Westinghouse on loading pattern design

 

      Temperature and power coefficients calculations

 

      COBRA-IV Sub-channel Analysis Code

. System of governing equations         

 

      COBRA-IV Sub-channel Analysis Code

. Plant Modeling Approach

      . Hot Assembly Analysis, treatment of hot channel factors

      . Core-Wide Analysis Approach, treatment of hot channel factors

 

      COBRA-IV plant modeling approach

 

COBRA-IV plant input/output.  Sample Plant Calculations

 

Meeting 4 with Westinghouse on RSAC Safety Calculations on final loading pattern. Introduction to operational calculations

                             

COBRA-IV calculations 

 

      Core loading pattern and safety analysis exam (Westinghouse test)

 

      Extended burnup and longer cycle length

                  C&T text – section 6.4

 

Economics and fuel cycle costs

 

            Meeting 5 with Westinghouse on operational calculations

 

            Presentation of Design Project, prepare final report

 

 

DESIGN PROJECT 

 

The course includes a design project based on a technical problem assignment for a PWR core design. Students are divided in teams to work on separate assignments under the supervision of a Westinghouse engineer. The Westinghouse core design codes are used and they are executed on a HP C3600 Visualize Workstation under UNIX operating system. The final design report is a formal design report that has to be composed of the technical results, written using the results of the reactor core design codes. The report has to be presented in both written orally formally (60 minutes synopsis of results), and has to include an executive summary, technical abstract, and assessment of the results (i.e. you must explain the results clearly and decide if they make sense) and conclusion sections.  A Poster Board Outline of your project, similar to those in the second floor of the Reber Building, should also be completed and given to Drs Ivanov and Hochreiter at the time of the presentation.

 

EVALUATION METHODS

 

The grading distributions are approximately as follows:

 

            Homework problems                                                                            20%

 

            First Exam (Core Neutronics Design Methods)                         20%

 

            Second Exam (Core Thermal-Hydraulics Design methods)                    20%

 

            Third Exam (Core loading patterns, safety analysis checks)                    15%

 

            Design Project                                                                                      25%

 

 

RELATIONSHIP TO OTHER COURSES

 

This class has prerequisites – NUC E 301, 302, 403 and 430.