Document: NUREG-0800
Document ID: 3ea2f0ac-4d7e-464a-b1c4-390c3970f642
Document Type: srp
Title: provides specific thermal-hydraulic criteria.  The available radioactive fission product
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070740002.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.4
CFR Part: 
CFR Title: 

Content:
truction of Nuclear Power Plant Components,” New York. 41. American Society for Testing and Materials, 1989 edition, Standard C776-89, Part 45, “Standard Specification for Sintered Uranium Dioxide Pellets,” Philadelphia, Pennsylvania. 42. W.J. O’Donnel and B.F. Langer, “Fatigue Design Basis for Zircaloy Components,” Nucl. Sci. Eng. 20, 1, 1964. 43. K. Joon, “Primary Hydride Failure of Zircaloy-Clad Fuel Rods,” Trans. Am. Nucl. Soc. 15, 186, 1972. 44. F. Erbacher, H.J. Neitzel, H. Rosinger, H. Schmidt, and K. Wiehr, “Burst Criterion of Zircaloy Fuel Claddings in a LOCA,” ASTM Fifth International Conference on Zirconium in the Nuclear Industry, August 4–7, 1980, Boston, Massachusetts. 45. G.A. Berna, C.E. Beyer, K.L. Davis, and D.D. Lanning, “FRAPCON-3: A Computer Code for the Calculation of Steady-State, Thermal-Mechanical Behavior of Oxide Fuel Rods of High Burnup,” NUREG/CR-6534 (PNNL-11513) Vol. 2, Pacific Northwest National Laboratory, December 1997. 4.2-27 Revision 3 - March 2007 46. D.D. Lanning, C.E. Beyer, and K.J. Geelhood, “FRAPCON-3 Updates, Including Mixed- Oxide Fuel Properties,” NUREG/CR-6534 (PNNL-11513) Vol. 4, Pacific Northwest National Laboratory, May 2005. 47. R.H. Stoudt, D.T. Buchanan, B.J. Buescher, L.L. Losh, H.W. Wilson, and P.J. Henningson, “TACO - Fuel Pin Performance Analysis, Revision 1,” Babcock & Wilcox Report BAW-10087A, Rev. 1, August 1977. 48. “Fuel Evaluation Model,” Combustion Engineering Report CENPD-139-A, July 1974 (Approved version transmitted to the NRC on April 25, 1975). 49. “Supplement 1 to the Technical Report on Densification of General Electric Reactor Fuels,” Atomic Energy Commission Regulatory Staff Report, December 14, 1973. 50. “Technical Report on Densification of Exxon Nuclear PWR Fuels,” Atomic Energy Commission Regulatory Staff Report, February 27, 1975. 51. Letter from J.F. Stolz, NRC, to T.M. Anderson, Westinghouse, Subject: Safety Evaluation of WCAP-8720, dated