Analysis of conventional and plutonium recycle unit-assemblies for the Yankee (Rowe) PWR
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856655148.pdf
Size
18.69 MB
Format
Adobe PDF
Checksum (MD5)
5fbefe3abd57cc2c6aa21c97ef54729c
Author(s)
Mertens, Paul Gustaaf
Date Issued
1971
Publisher
Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1971]
Series/Report no.
MITNE ; no. 134
Abstract
An analysis and comparison of Unit Conventional UO2 Fuel-Assemblies and proposed Plutonium Recycle Fuel Assemblies for the Yankee (Rowe) Reactor has been made. The influence of spectral effects, at the watergaps -and spectral-and transport effects at the UO2 - Mixed Oxide interface, on the powerpeaking has been determined. Two one thermal group methods have been developed for the calculation of powerpeaking in the two dimensional assemblies. The accuracy of the LEOPARD code and LASER code (thermal cut off 1.855 ev) for the calculation of the powerpeaking in conventional and plutonium recycle assemblies has been evaluated. The power distribution and local power peaking factors during burnup, including spectral effects, were also calculated with a macroscopic depletion model. Power gradients inside the peak UO2 rod and peak mixed oxide rod were also determined, and the variations in the heat flux, at the pellet and cladding surface, around these peak pins were calculated. Finally preliminary comparisons of engineering factors for the peak U02 rod and the peak mixed oxide rod have been made.
Description
Cover title
At head of title, "Draft report."
"November 1971."
Includes bibliographical references (pages 299-303)
Draft report; November 1971
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