An Analytical Study of Azimuthal Temperature Distribution in Pressurized Water Reactor Fuel Rods Under Steady-State and Blowdown Conditions-Reference-Cited by-同舟云学术

An Analytical Study of Azimuthal Temperature Distribution in Pressurized Water Reactor Fuel Rods Under Steady-State and Blowdown Conditions

Published:1982-06 Issue:3 Volume:57 Page:331-342
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Sdouz Gert¹,Dagbjartsson Sigurdur J.²

Affiliation:

1. Austrian Research Center Seibersdorf, A-1082 Vienna, Austria

2. Fa. Fichtner, Consulting Engineers, D-7000 Stuttgart, West Germany

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT82-A26302

Reference10 articles.

1. K. WIEHR et al. “Projekt Nukleare Sicherheit Halbjah-resbericht 1977/2,” KFK-2600, p. 383, Kernforschungszentrum Karlsruhe (May 1978).

2. R. H. CHAPMAN, “Multirod Burst Test Program Quarterly Progress Report for April-June 1977,” ORNL/NUREG/TM-135, Oak Ridge National Laboratory (Dec. 1977).

3. L. J. SIEFKEN et al. “FRAP-T4, A Computer Code for the Transient Analysis of Oxide Fuel Rods,” CDAP-TR-78-027, EG&G, Idaho, Inc. (July 1978).

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

2. Determination of Transient Radial-Azimuthal Temperature Distributions in Fuel Bundles Under Loss-of-Coolant-Accident Conditions;Nuclear Technology;1988-10

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

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