Azimuthal temperature variation in the cladding of PWR fuel elements-Reference-Cited by-同舟云学术

Azimuthal temperature variation in the cladding of PWR fuel elements

Published:1984-01 Issue:1 Volume:77 Page:97-102
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Barrow H.,Hassan A.K.A.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference7 articles.

1. Nuclear Reactor Engineering;Glasstone,1981

2. Heat transfer in the vicinity of a partial flow blockage in a reactor core;Hall,1977

3. Azimuthal temperature variations due to convective cooling of ballooned PWR fuel cladding, C.E.G.B.;Board,1981

4. The prediction of forced convection in a cusp-shaped channel;Haque,1982

5. A.K.A. Hassan, H. Barrow, M.A. Haque and J.T. Turner, Prediction of the peripheral temperature variation in fuel rod cladding due to blockage resulting from a LOCA (in preparation).

Cited by 5 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Exact solution to the conjugate problem of nonuniform cooling of fuel rods;International Journal of Heat and Fluid Flow;1991-06

2. An Approach to the Prediction of Cladding Azimuthal Temperature in a Light Water Reactor Four-Cusp Channel;Nuclear Science and Engineering;1988-09

3. Variational Determination of Transient Radial-Azimuthal Temperature Distributions in Fuel Rods for Loss-of-Coolant-Accident Analysis;Nuclear Technology;1988-08

4. Heat transfer in the corners of noncircular ducts with peripherally uniform wall heat flux;International Journal of Heat and Mass Transfer;1985-04

5. Peripheral temperature variation in the wall of a noncircular duct — An experimental investigation;International Journal of Heat and Mass Transfer;1984-07