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:
tomic Energy Commission Regulatory Staff Report, November 14, 1972. 26. NUREG-75/077, “The Role of Fission Gas Release in Reactor Licensing,” November 1975. 27. NUREG-0085, “The Analysis of Fuel Densification,” July 1976. 28. NUREG-0303, “Evaluation of the Behavior of Waterlogged Fuel Rod Failures in LWRs,” March 1978. 29. NUREG-0308, Supp. 2, “Safety Evaluation Report Related to Operation of Arkansas Nuclear One, Unit 2,” September 1978. 30. NUREG-0401, “Fuel Failure Detection in Operating Reactors,” March 1978. 4.2-26 Revision 3 - March 2007 31. NUREG-0418, “Fission Gas Release from Fuel at High Burnup,” March 1978. 32. NUREG-0609, “Asymmetric Blowdown Loads on PWR Primary Systems,” January 1981. 33. NUREG-0630, “Cladding Swelling and Rupture Models for LOCA Analysis,” April 1980. 34. NUREG/CR-1018, “Review of LWR Fuel System Mechanical Response with Recommendations for Component Acceptance Criteria,” September 1979. 35. NUREG/CR-1019, “Pressurized Water Reactor Lateral Core-Response Routine, FAMREC (Fuel Assembly Mechanical Response Code),” September 1979. 36. NUREG/CR-1020, “Technical Evaluation of PWR Fuel Spacer Grid Response Load Sensitivity Studies,” September 1979. 37. NUREG/CR-1380, “Assessment of Current Onsite Inspection Techniques for LWR Fuel Systems,” Vol. 1, July 1980; Vol. 2, January 1981. 38. NUREG/CR-1883, “Multirod Burst Test Program Progress Report for January–June 1980,” March 1981. 39. American National Standards Institute, ANSI/ANS 5.4, “Method for Calculating the Fractional Release of Volatile Fission Products from Oxide Fuel,” American Nuclear Society, November 10, 1982. 40. American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III, “Rules for Construction 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