.. _section-8.8:

References
----------

8-1. D.R. MacFarlane, Ed., "SAS1A, A Computer Code for the Analysis of
Fast Reactor Power and Flow Transients," ANL-7606, Argonne National
Laboratory, October 1970.

8-2. F.E. Dunn, et al., "The SAS2A LMFBR Accident Analysis Computer Code,"
ANL-8138, Argonne National Laboratory, October 1974.

8-3. F.E. Dunn, et al, Unpublished information, Argonne National
Laboratory, 1975.

8-4. J.E. Cahalan and D.R. Ferguson, Ed., Unpublished information, Argonne
National Laboratory, 1977.

8-5. Energy Research and Development Administration, Unpublished
information, 1977.

8-6. M. Bober and G. Schumacher, "Material Transport in the Temperature
Gradient of Fast Reactor Fuels," *Adv. Nucl. Sci. Tech.*, vol. 7, p.
121-196, 1973.

8-7. C.F. Clement, "The Movement of Lenticular Pores in UO\ :sub:`2`
Nuclear Fuel Elements," *J. Nucl. Mat.*, vol. 68, p. 63-68, 1977.

8-8. W.F. Lackey, F.J. Homan, A.R. Olsen, "Porosity and Actinide
Redistribution During Irradiation of (U Pu) O\ :sub:`2`," *Nucl.
Technol.*, vol. 16, p. 120-142, 1972.

8-9. F.A. Nichols, "The Theory of Grain Growth in Porous Compacts,"
*Journal of Applied Physics*, vol. 37, no. 13, p. 4599-4602, 1966.

8-10. R.N. Singh, "Isothermal Grain Growth Kinetics in Sintered Pellets,"
*J. Nucl. Mat.*, vol. 64, p. 174-178, 1977.

8-11. G.A. Reymann, Ed., "MATPRO-VERSION 10: A Handbook of Materials
Properties for Use in the Analysis of Light Water Reactor Fuel Rod
Behavior," TREE-NUREG-1180, EG & G Idaho, Inc., 1978.

8-12. J.B. Ainscough, B.W. Oldfield and J.O. Ware, "Isothermal Grain Growth
Kinetics in Sintered UO\ :sub:`2` Pellets," *J. Nucl. Mat.*, vol. 49, p.
117-128, 1973-74.

8-13. J. Rest, Unpublished information, Argonne National Laboratory, 1978.

8-14. E.E. Gruber, "A Generalized Parametric Model for Transient Gas
Release and Swelling in Oxide Fuels," *Nucl. Technol.*, vol. 35, p.
617-634, October 1977.

8-15. J. Weisman, et al., "Fission Gas Release from UO\ :sub:`2` Fuel Rods
with Time-Varying Power Histories," *Trans. Am. Nucl. Soc.*, vol. 12, p.
900, 1969.

8-16. J.A. Dearien, et. al. "FRAP-S2: A Computer Code for the Steady State
Analysis of Oxide Fuel Rods," TREE-NUREG-1107, EG & G Idaho, Inc., July
1977.

8-17. Hanford Engineering Development Laboratory, Unpublished information,
1971.

8-18. A.M. Ross, R.L. Stoute, "Heat Transfer Coefficients Between
UO\ :sub:`2` and Zircalloy 2," AECL-1552, Atomic Energy of Canada, LTD,
1962.

8-19. G.R. Horn and F.E. Panisko, Unpublished information, Hanford
Engineering Development Laboratory, 1972.

8-20. M. Knudsen, "The Kinetic Theory of Gases--Some Modern Aspects,"
Methuen and Co, Ltd, 2nd Edition, 1946.

8-21. Lassmann and F. Pazdera, "URGAP, A Gap Conductance Model for
Transient Conditions," Water Reactor Fuel Element Performance Modeling,
edited by J. Gittos, Applied Science Publishers, :numref:`Chapter %s<section-3>`, pp. 97-113,
1983.

8-22. W.R. Bohl, et al., Unpublished information, Argonne National
Laboratory, 1975.

8-23. C. Essig, et al., "Dynamic Behavior of RAPSODIE in Exceptional
Transient Experiments, "CONF-850410, Proc. of the Intl. Topical Meeting
on Fast Reactor Safety, Knoxville, Tennessee, p. 635, April 1985.

8-24. E. E. Gruber and J. M. Kramer, Unpublished information, Argonne
National Laboratory, 1985.

8-25. L. C. Walter, B. R. Seidel, and J. H. Kittel, "Performance of
Metallic Fuels and Blankets in Liquid-Metal Fast Breeder Reactors,"
*Nucl. Technol.*, vol. 65, p. 179, 1984.

8-26. B. R. Seidel and L. C. Walters, "EBR-II Metallic Driver Fuel - A Live
Option," *J. Eng. Power*, vol. 103, p. 612, 1981.

8-27. G. Birgersson, et al., Unpublished information, Argonne National
Laboratory, 1983.

8-28. K. J. Miles, Jr. and Kalimullah, "The Inherent Safety Phenomenon of
Fission-Gas Induced Axial Extrusion in Oxide and Metal Fueled LMFBRs,"
CONF-850410, Proc. of the Intl. Topical Meeting on Fast Reactor Safety,
Knoxville, Tennessee, p. 103, April 1985.

8-29. W. R. Robinson, et al., Unpublished information, Argonne National
Laboratory, 1985.

8-30. F.E. Bard, Unpublished information, Hanford Engineering Development
Laboratory, 1982.

8-31. D.S. Dutt, et al., Unpublished information, Hanford Engineering
Development Laboratory, 1973.

8-32. S.Y. Ogawa, E.A. Lees and M.F. Lyons, "Power Reactor High Performance
UO\ :sub:`2` Program, Fuel Design Summary and Progress Status,"
GEAP-5591, General Electric Company, 1968.

8-33. P. Verbeek and H. Hoppe, "COMETHE-IIIJ: A Computer Code for
Predicting Mechanical and Thermal Behavior of a Fuel Pin, Part 1,
General Description," INBFR-107 (original report BN-7609-07,
Belgonucleaire, Brussels, Belgium, 1977.

8-34. R.J. DiMelfi and J.M. Kramer, "Modeling the Effects of Fast-Neutron
Irradiation on the Subsequent Mechanical Behavior of Type 316 Stainless
Steel," *J. of Nucl. Mat.*, vol. 89, no. 2 & 3, pp. 338-346, 1980.

8-35. R.B. Baker, "Calibration of a Fuel-to-Cladding Gap Conductance Model
for Fast Reactor Fuel Pins," HEDL-TME-77-86, Hanford Engineering
Development Laboratory, May 1978.

8-36. T. H. Hughes, Unpublished information, Argonne National Laboratory,
1985.

8-37. J. M. Kramer, private communication, October 1984.

8-38. D.R. Olander, "Fundamental Aspects of Nuclear Reactor Fuel Elements,"
TID-26711-Pl, Energy Research and Development Administration, 1976.


8.39. N. Cautaerts, et al., “Thermal Creep Properties of Ti-Stabilized DIN 1.4970 (15-15Ti) Austenitic Stainless Steel Pressurized Cladding Tubes,” *Journal of Nuclear Materials*, Vol. 493, pp. 154-67, (2017).

8.40. J. L. Seran, et al., “Behavior under Neutron Irradiation of the 15-15Ti and EM10 Steels Used as Standard Materials of Phenix Fuel Assemblies,” ASTM STP 1125, pp. 1209-1233, (1992).

8.41. N. Miyaji, et al., “Post-irradiation Creep Rupture Properties of FBR grade 316 SS Structural Material,” *Journal of Nuclear Materials*, Vol. 271, pp. 173-178, (1999).

8.42. S. Ukai, et al., “In-reactor Creep Rupture Properties of 20% CW Modified 316 Stainless Steel,” *Journal of Nuclear Materials*, Vol. 278, pp. 320-327, (2000).

8.43. R. J. Puigh, et al., “In-Reactor Creep Rupture Behavior of the D19 and 316 Alloys,” *Influence of Radiation on Material Properties: 13th International Symposium – Part II*, ASTM STP 956, pp. 22-29, (1987).