Analysis of conventional and plutonium recycle unit-assemblies for the Yankee (Rowe) PWR

Cover title

Bibliographic Details
Main Author: Mertens, Paul Gustaaf
Other Authors: Massachusetts Institute of Technology. Department of Nuclear Engineering
Format: Technical Report
Published: Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1971] 2014
Subjects:
Online Access:http://hdl.handle.net/1721.1/89709
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author Mertens, Paul Gustaaf
author2 Massachusetts Institute of Technology. Department of Nuclear Engineering
author_facet Massachusetts Institute of Technology. Department of Nuclear Engineering
Mertens, Paul Gustaaf
author_sort Mertens, Paul Gustaaf
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spelling mit-1721.1/897092019-04-12T14:14:01Z Analysis of conventional and plutonium recycle unit-assemblies for the Yankee (Rowe) PWR Mertens, Paul Gustaaf Massachusetts Institute of Technology. Department of Nuclear Engineering TK9008.M41 N96 no.134 Yankee Atomic Power Plant (Mass.) Plutonium -- Recycling Pressurized water reactors Nuclear fuel rods Cover title At head of title, "Draft report." "November 1971." Includes bibliographical references (pages 299-303) Draft report; November 1971 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. 2014-09-16T23:32:33Z 2014-09-16T23:32:33Z 1971 Technical Report http://hdl.handle.net/1721.1/89709 856655148 MITNE ; no. 134 303 pages application/pdf Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1971]
spellingShingle TK9008.M41 N96 no.134
Yankee Atomic Power Plant (Mass.)
Plutonium -- Recycling
Pressurized water reactors
Nuclear fuel rods
Mertens, Paul Gustaaf
Analysis of conventional and plutonium recycle unit-assemblies for the Yankee (Rowe) PWR
title Analysis of conventional and plutonium recycle unit-assemblies for the Yankee (Rowe) PWR
title_full Analysis of conventional and plutonium recycle unit-assemblies for the Yankee (Rowe) PWR
title_fullStr Analysis of conventional and plutonium recycle unit-assemblies for the Yankee (Rowe) PWR
title_full_unstemmed Analysis of conventional and plutonium recycle unit-assemblies for the Yankee (Rowe) PWR
title_short Analysis of conventional and plutonium recycle unit-assemblies for the Yankee (Rowe) PWR
title_sort analysis of conventional and plutonium recycle unit assemblies for the yankee rowe pwr
topic TK9008.M41 N96 no.134
Yankee Atomic Power Plant (Mass.)
Plutonium -- Recycling
Pressurized water reactors
Nuclear fuel rods
url http://hdl.handle.net/1721.1/89709
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