Document: NUREG-0800
Document ID: 28c03fd2-3542-41ec-bfd7-5df2087c4ee6
Document Type: srp
Title: FUEL SYSTEM DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070407.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.2
CFR Part: 
CFR Title: 

Content:
2337. NUREG/CR-1018R. L. Grubb, "Review of LWR Fuel System Mechanical Response with Recommendations for Component Acceptance Criteria," Idaho National Engineering Laboratory, NUREG/CR-1018, September 1979. 2438. NUREG/CR-1019R. L. Grubb, "Pressurized Water Reactor Lateral Core-Response Routine, FAMREC (Fuel Assembly Mechanical Response Code)," Idaho National Engineering Laboratory, NUREG/CR-1019, September 1979. 2539. NUREG/CR-1020R. L. Grubb, "Technical Evaluation of PWR Fuel Spacer Grid Response Load Sensitivity Studies," Idaho National Engineering Laboratory, NUREG/CR-1020, September 1979. 2633. NUREG/CR-1380W. J. Bailey, et al., "Assessment of Current Onsite Inspection Techniques for LWR Fuel Systems," Battelle Pacific Northwest Laboratory Report NUREG/CR-1380, Vol. 1, July 1980, Vol. 2, January 1981. 2713. NUREG/CR-1883R. H. Chapman, "Multirod Burst Test Program Progress Report for January-June 1980," Oak Ridge National Laboratory Report NUREG/CR-1883, March 1981. 28. American National Standard Institute, ANSI/ANS 5.4, "Method for Calculating the Fractional Release of Volatile Fission Products from Oxide Fuel," American Nuclear Society, November, 10, 1982.94 294. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, 1977 edition, Section III, "Rules for Construction of Nuclear Power Plant Components," 95 ASME Boiler and Pressure Vessel Code, Section III, 1977New York. 307. American Society for Testing and Materials, 198977 edition, Standard C776-8976 , Part 96 45, "Standard Specification for Sintered Uranium Dioxide Pellets," Philadelphia. 315. W. J. O'Donnel and B. F. Langer, "Fatigue Design Basis for Zircaloy Components," Nucl. Sci. Eng. 20, 1 (1964). 4.2-21 DRAFT Rev. 3 - April 1996 328. K. Joon, "Primary Hydride Failure of Zircaloy-Clad Fuel Rods," Trans. Am. Nucl. Soc. 15, 186 (1972). 3312. F. Erbacher, H. J. Neitzel, H. Rosinger, H. Schmidt, and K. Wiehr, "Burst Criterion of Zircaloy Fuel Claddings in a LOCA," ASTM Fifth