Published September 1977 | Version v1
Report Open

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.

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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