Legend
Problem assignments from the assigned texts are given in the following format:
T-C(P)
T = Text Number
C = Chapter Number
P = Problem Number
Other problem statements are provided on the assignments page.
Key for readings:
* Readings in Text 1
† Readings in Text 2
£ Readings in Text 3
‡ Readings in Text 4
¥ Readings in Text 6
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DAY # |
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TOPICS |
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PROBLEMS |
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READINGS |
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HANDOUTS |
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1 |
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Introduction, Definitions, Flow Patterns |
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8-1(1)
8-2(3), (4); 2-5(3) |
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*Sec. 3.1, 3.2 (pp. 119-147)
† Ch. 5 (to pp. 144) Ch. 11 (pp. 462-476)
‡Sec. 4.1 - 4.3.1 (pp. 159-166)
Sec. 4.3.9 – 4.3.10 (pp. 187–192)
Sec. 4.4.7 - 4.4.8 (pp. 207-211)
Sec. 4.6 (pp. 221-222) |
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2 |
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Bubbly and Slug Flow |
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8-3(6) |
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*Sec. 3.4.4 - 3.4.5 (pp. 173-177)
‡Sec. 4.3 - 4.5 (pp. 162-220) |
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3 |
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Annular Flow |
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SS-1 |
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*Sec. 3.4.6 (pp. 177-182)
‡Sec. 4.6 (pp. 221-255)
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4 |
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Homogeneous Flow |
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8-5(11), (12)
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*Sec. 3.4, 3.4.1 (pp. 168-169)
† Ch. 11 (pp. 485-490)
‡Sec. 3.4 (pp. 98-107) |
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5 |
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Separated Flow |
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OO-2, OO-3 |
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*Sec. 3.4.2 (pp. 170-172)
† Ch. 11 (pp. 490-507)
‡Sec. 3.5 (pp. 107-124) |
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Note 1
Note 2 |
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6 |
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Separated Flow (cont.) |
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7 |
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Drift Flux |
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8-7(18), (20);
PP-1 |
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*Sec. 3.4.1 (pp. 168-170)
† Ch. 11 (pp. 478-491) |
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8 |
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Deposition, Entrainment, Separation, Flooding |
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8-9(25), (26);
8-11(28) |
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*Sec. 3.4.6.2 (pp. 180)
† Ch. 11 (pp. 464-466) |
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Multiphase Science and Technology 1 |
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9 |
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Nucleation -- Pool and Flow Boiling |
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*Sec. 2.2.2 - 2.4.2 (pp. 20-79)
† Ch. 12 (pp. 523-525) |
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10 |
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Nucleation -- Continued, Pool Boiling Heat Transfer |
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8-14(33); BB-2 |
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*Sec. 2.4.3 - 2.5 (pp. 80-118)
Sec. 4.1 - 4.33 (pp. 245-268)
† Ch. 12 (pp. 525-527) |
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11 |
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Pool Boiling and Film Boiling CHF, Flow Boiling Heat Transfer pre CHF |
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DD-2; FF-8 |
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*Sec. 2.4.3 - 2.5 (pp. 80-117)
Sec. 4.1 - 4.3 (pp. 245-265)
† Ch. 12 (pp. 527-546)
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Note 3 |
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12 |
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Two Phase Flow Modeling |
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*Sec. 2.1 - 2.2.1.2 (pp. 7-19)
† Ch. 5 (pp. 125-128) |
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13 |
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Two Phase Flow Modeling |
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14 |
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Critical Flow |
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8-8(22); RR-2 |
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*Sec. 3.6 (pp. 219-239)
† Ch. 11 (pp. 507-517)
‡Ch. 6 (pp. 300-355) |
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15 |
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Flow Boiling CHF |
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*Sec. 5.1 - 5.4 (pp. 303-400)
† Ch. 12 (pp. 534-537) and (pp. 554-570) |
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NED Papers2 |
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Take Home Quiz Out -- All references allowed but do not discuss this quiz,
and your solutions with ANYONE
until it has been handed in for grading. |
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16 |
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Flow Boiling CHF
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JJ-7
Take Home Quiz due
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*Sec. 5.5 (pp. 401 - 456) |
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NED Papers3 |
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17 |
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Post CHF |
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UU-1 |
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*pp. 274-297
† Ch. 12 (pp. 546-554)
¥ (pp. 279 - 303) |
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Special References |
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18 |
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Flow Instabilities - Ledinegg, Density Wave |
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HH-2 |
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*Ch. 6 - complete(pp. 457-480)
† Ch. 13 (pp. 592-596) |
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Special References |
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19 |
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Formulation of the Reactor Thermal Hydraulic Design Problem |
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3-1(1) |
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£ - Ch. 1 (pp. 1-23) |
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20 |
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Natural Circulation |
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3-3(1) |
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£ - Ch. 3 (pp. 67-93) |
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MITNPI-TR-0394 |
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21 |
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Multiple Heated Channels Connected Only at Plena |
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3-4(4) |
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£ - Ch. 4, Sec. I through VII |
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22 |
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Multiple Heated Channels Connected Only at Plena (cont.) |
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£ - Ch. 4, Sec. VIII |
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23 |
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Subchannel Analysis: Conservation Equations |
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£ - Ch. 6, Sec. I through IV |
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24 |
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Subchannel Analysis: Constitutive Equations |
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3-6(3) |
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£ - Ch. 6, Sec. VII |
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25 |
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Subchannel Analysis: Applications |
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£ - Ch. 6, Sec. VIII |
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26 |
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Thermal Design Process |
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Term Project
due |
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AP6005 |
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Supplemental Reading
1 Griffith, P. "Steam Water Separation." Multiphase Science and Technology 9, 4 (1997): 381-437.
2 Hejzlar, P., and N. E. Todreas. "Consideration of Critical Heat Flux Prediction by Subcooled or Low Quality Critical Heat Flux Correlations." Nuclear Engineering and Design, 163 (1996): 215-223.
Letter: "Response of Hejzlar and Todreas to Contributors' Letters and Technical Notes." Nuclear Engineering and Design, 163 (1996): 273-279.
3 Olekhnovitch, A., A. Teyssedou, and P. Tye. "On The Round Table Discussion on Reactor Power Margins Published in Nuclear Engineering and Design 163 (1-2), 1996." Nuclear Engineering and Design, 201 (2000): 335-346.
Hejzlar, P., and N. E. Todreas. "Response to Letter to the Editor." Nuclear Engineering and Design, 201 (2000): 347-352.
4 Yesilyurt, Driscoll, and Todreas. "Numerical Calculation of Mixed Convection in a Duct under MHTGR Conditions." MITNPI-TR-039 (June 1991): 12-38.
5 AP600 -- Design Control Document. Section 4.4 -- Thermal Hydraulic Design.
Reading Materials for Post-CHF Heat Transfer (Lecture 17)
- Pradip Saha, “A Nonequilibrium Heat Transfer Model for Dispersed Droplet Post-Dryout Regime,” International Journal of Heat and Mass Transfer, Vol. 23, pp. 483 – 492, 1980.
- John C. Chen, “A Short Review of Dispersed Flow Heat Transfer in Post-Dryout Boiling,” Nuclear Engineering and Design, Vol. 95, pp. 375 – 383, 1986.
- A. F. Varone and W. M. Rohsenow, “The Influence of the Dispersed Phase on the Convective Heat Transfer in Dispersed Flow Film Boiling,” MIT Report No. 71999-106, Heat Transfer Lab, January 1990.
- M. Andreani and G. Yadigaroglu, “Prediction Methods for Dispersed Flow Film Boiling,” International Journal of Multiphase Flow, Vol. 20, Supplement, pp. 1 – 51, 1994.
- J. M. Kelly, “Constitutive Model Development for Reactor Safety Thermal-Hydraulic Codes,” Invited Lecture at MIT for Course 22.313, March 20, 2003.
Reading Materials for Two-Phase Flow Instabilities (Lecture 18)
- Lahey, R. T., Jr., and F. J. Moody. Thermal Hydraulics of a Boiling Water Nuclear Reactor. ANS, 1977. Chap. 7 (Boiling Water Reactor Stability Analysis).
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Saha, P., M. Ishii, and N. Zuber. "An Experimental Investigation of Thermally Induced Flow Oscillations in Two-Phase Systems." Journal of Heat Transfer 98 (1976): 616-622. (Also ASME Paper No. 75-WA/HT-6)
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Rizwan-Uddin. "On Density-Wave Oscillations in Two-Phase Flows." International Journal of Multiphase Flow 20, 4 (1994): 721-737.
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Khabensky, Vladimir B., and Vladimir A. Gerliga. Hydrodynamic Flow Instabilities in Power Equipment Components. New Delhi, India: CBS Publishers and Distributors, 1995.