Published September 1977
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Axial gas flow in irradiated PWR fuel rods
Description
Transient and steady state axial gas flow experiments were performed on six irradiated, commercial pressurized water reactor fuel rods at ambient temperature and 533 K. Laminar flow equations, as used in the FRAP-T2 and SSYST fuel behavior codes, were used with the gas flow results to calculate effective fuel rod radial gaps. The results of these analyses were compared with measured gap sizes obtained from metallographic examination of one fuel rod. Using measured gap sizes as input, the SSYST code was used to calculate pressure drops and mass fluxes and the results were compared with the experimental gas flow data
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A06/MF A01.Files
9365883.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 105 p.
- Report number
- TREE-NUREG--1158
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 9365883
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- DIFFUSION; FUEL RODS; GAS FLOW; MASS TRANSFER; PRESSURE DROP; PWR TYPE REACTORS
- Descriptors DEC
- FLUID FLOW; FUEL ELEMENTS; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS