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:
ould be reviewed include the following: • Radial power distribution • Fuel and cladding temperature distribution • Burnup distribution in the fuel • Thermal conductivity of the fuel, cladding, cladding crud, and oxidation layers • Densification of the fuel • Thermal expansion of the fuel and cladding • Fission gas production and release • Solid and gaseous fission product swelling • Fuel restructuring and relocation 4.2-16 Revision 3 - March 2007 • Fuel and cladding dimensional changes • Fuel-to-cladding heat transfer coefficient • Thermal conductivity of the gas mixture • Thermal conductivity in the Knudsen domain • Fuel-to-cladding contact pressure • Heat capacity of the fuel and cladding • Growth and creep of the cladding • Rod internal gas pressure and composition • Sorption of helium and other fill gases • Cladding oxide and crud layer thickness • Cladding-to-coolant heat transfer coefficient • Cladding hydriding Because of the strong interaction between these models, overall code behavior should be checked against data (standard problems or benchmarks) and the NRC audit codes. NUREG/CR-6534 (PNNL- 11513) Vol. 2, December 1997, FRAPCON-3 NUREG/CR-6534 (PNNL- 11513) Vol. 4, May 2005, Babcox & Wilcox Report BAW-10087A, Rev. 1, August 1977, CENPD-139-A, July 1974, Supplement 1 to Technical Report on General Electric Reactor Fuels, December 14, 1973, Technical Report on Exxon Nuclear PWR Fuels, February 27, 1975, and the Letter on Westinghouse Safety Evaluation of WCAP-8720, February 9, 1979, provide examples of previous fuel performance code reviews. ii. Densification Effects. In addition to its effect on fuel temperatures (discussed above), densification affects (1) core power distributions (power spiking - see SRP Section 4.3), (2) the fuel linear heat generation rate (LHGR) - see SRP Section 4.4, and (3) the potential for cladding collapse. NUREG-0085 and RG 1.126 discuss densification magnitudes for power spike and