NUCLEAR
SYSTEMS II Second Edition
Elements of Thermal
Hydraulic Design
SOLUTION MANUAL
Second Edition
December 2021
Neil E. Todreas
Mujid S. Kazimi Mahmoud Massoud
Nuclear Systems II, 2nd edition - Solution Manual 1
, CONTENTS
Chapter 1. Formulation of the Reactor Thermal Hydraulic Design Problem ......................... 5
Chapter 2. Scaling of Two-Phase Flows in Complex Nuclear Reactor Systems ................... 12
Chapter 3. Single, Heated Channel Transient Analysis.......................................................... 18
Chapter 4. Multiple Heated Channels Connected Only at Plena ............................................ 37
Chapter 5. Analysis of Interacting Channels by the Porous Media Approach ....................... 73
Chapter 6. Analysis of Interacting Channels by the Subchannel Approach ........................... 95
Chapter 7. Flow Loops ........................................................................................................... 118
Chapter 8. Steady State and Transient Analysis of Centrifugal Pumps ................................. 144
Chapter 9. Thermal Analysis of Pressurizers ......................................................................... 179
Chapter 10. Thermal Analysis of Containments ...................................................................... 198
Chapter 11. Thermal Analysis of Steam Generators and Condensers...................................... 219
Chapter 12. Fundamentals of Reactor Transient Simulation.................................................... 248
Chapter 13. Treatment of Uncertainties in Reactor Thermal Analysis .................................... 273
Nuclear Systems II, 2nd edition - Solution Manual 4
, Solution Manual – Chapter 1
Chapter 1
Formulation of the Reactor Thermal Hydraulic
Design Problem
Contents
Problem 1.1 Boundary conditions for flow transients in test loops ............................................ 6
Problem 1.2 Boundary conditions for a multiple channel representation of a reactor system .... 10
Nuclear Systems II, 2nd edition - Solution Manual 5
, Solution Manual – Chapter 1
PROBLEM 1.1 QUESTION
Boundary conditions for flow transients in test loops (Sections 1.5 and 1.7)
Identify the hydraulic and thermal boundary condition sets applicable for analysis of the three
test sections described below in a loss of flow transient with constant power. Consider the cases
of each test section located in the test loops sketched in Figures 1.12 and 1.13.
Test section 1. Single channel with a flow blockage that reduces the cross-sectional area for flow
by 50% at the axial mid-position.
Test section 2. Two interconnected channels, one of which has a flow blockage as described for
test section 1.
Test section 3. Twenty interconnected channels, one of which has a flow blockage as described
for test section 1.
Note that this problem requires six answers as illustrated below.
Test section
Case 1 Case 2 Case 3
Loop A
Loop B
FIGURE 1.12 Loop A.
Nuclear Systems II, 2nd edition - Solution Manual 6
SYSTEMS II Second Edition
Elements of Thermal
Hydraulic Design
SOLUTION MANUAL
Second Edition
December 2021
Neil E. Todreas
Mujid S. Kazimi Mahmoud Massoud
Nuclear Systems II, 2nd edition - Solution Manual 1
, CONTENTS
Chapter 1. Formulation of the Reactor Thermal Hydraulic Design Problem ......................... 5
Chapter 2. Scaling of Two-Phase Flows in Complex Nuclear Reactor Systems ................... 12
Chapter 3. Single, Heated Channel Transient Analysis.......................................................... 18
Chapter 4. Multiple Heated Channels Connected Only at Plena ............................................ 37
Chapter 5. Analysis of Interacting Channels by the Porous Media Approach ....................... 73
Chapter 6. Analysis of Interacting Channels by the Subchannel Approach ........................... 95
Chapter 7. Flow Loops ........................................................................................................... 118
Chapter 8. Steady State and Transient Analysis of Centrifugal Pumps ................................. 144
Chapter 9. Thermal Analysis of Pressurizers ......................................................................... 179
Chapter 10. Thermal Analysis of Containments ...................................................................... 198
Chapter 11. Thermal Analysis of Steam Generators and Condensers...................................... 219
Chapter 12. Fundamentals of Reactor Transient Simulation.................................................... 248
Chapter 13. Treatment of Uncertainties in Reactor Thermal Analysis .................................... 273
Nuclear Systems II, 2nd edition - Solution Manual 4
, Solution Manual – Chapter 1
Chapter 1
Formulation of the Reactor Thermal Hydraulic
Design Problem
Contents
Problem 1.1 Boundary conditions for flow transients in test loops ............................................ 6
Problem 1.2 Boundary conditions for a multiple channel representation of a reactor system .... 10
Nuclear Systems II, 2nd edition - Solution Manual 5
, Solution Manual – Chapter 1
PROBLEM 1.1 QUESTION
Boundary conditions for flow transients in test loops (Sections 1.5 and 1.7)
Identify the hydraulic and thermal boundary condition sets applicable for analysis of the three
test sections described below in a loss of flow transient with constant power. Consider the cases
of each test section located in the test loops sketched in Figures 1.12 and 1.13.
Test section 1. Single channel with a flow blockage that reduces the cross-sectional area for flow
by 50% at the axial mid-position.
Test section 2. Two interconnected channels, one of which has a flow blockage as described for
test section 1.
Test section 3. Twenty interconnected channels, one of which has a flow blockage as described
for test section 1.
Note that this problem requires six answers as illustrated below.
Test section
Case 1 Case 2 Case 3
Loop A
Loop B
FIGURE 1.12 Loop A.
Nuclear Systems II, 2nd edition - Solution Manual 6
