PU Disposition in Russian VVERs: Physics Studies of Lead Test Assembly Design

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As part of Fissile Materials Disposition Program (FMDP) physics support was given to the design of a MOX lead test assembly (LTA) for use in Russian VVER nuclear reactors. This paper discusses some of the pertinent findings and assessments for two distinct LTA designs for weapons-grade (WG) Pu dispositioning in Russian VVER-1000 nuclear reactors. The two assessed MOX LTA designs are the graded-zone full MOX LTA and the Island LTA (2 central zones of MOX pins surrounded by UO{sub 2} pins). The process of optimizing the graded Pu-content by zone in the fuel assembly is discussed. Eigenvalue and power peaking ... continued below

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18 pages

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Ellis, R. J. May 7, 2000.

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Description

As part of Fissile Materials Disposition Program (FMDP) physics support was given to the design of a MOX lead test assembly (LTA) for use in Russian VVER nuclear reactors. This paper discusses some of the pertinent findings and assessments for two distinct LTA designs for weapons-grade (WG) Pu dispositioning in Russian VVER-1000 nuclear reactors. The two assessed MOX LTA designs are the graded-zone full MOX LTA and the Island LTA (2 central zones of MOX pins surrounded by UO{sub 2} pins). The process of optimizing the graded Pu-content by zone in the fuel assembly is discussed. Eigenvalue and power peaking comparisons are made as a function of fuel burnup. Zero-power reactivity effects were calculated for the different LTA options. For the ORNL results, the n,{gamma}-transport lattice physics code HELIOS-1.4 was used with nuclear data libraries (based on ENDF/B-VI) in 89 and 190 neutron energy groups. Some comparisons are made between the ORNL HELIOS results and corresponding Russian LTA calculations by the RRC-KI (Kurchatov Institute) using the code TVS-M. Also in this paper, pertinent results are discussed from a study of void reactivity effects for LEU, RG MOX and WG MOX fuels in PWR and VVER-1000 nuclear reactors. These void reactivity calculations were performed for a large range of LEU enrichments (2-20 wt% {sup 235}U), and large ranges of Pu-content (2-20 wt% Pu) in RG and WG MOX fuel.

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18 pages

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INIS; OSTI as DE00771483

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  • Physor 2000, Pittsburgh, PA (US), 05/07/2000--05/11/2000

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  • Report No.: P00-106294
  • Grant Number: AC05-00OR22725
  • Office of Scientific & Technical Information Report Number: 771483
  • Archival Resource Key: ark:/67531/metadc724481

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Office of Scientific & Technical Information Technical Reports

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  • May 7, 2000

Added to The UNT Digital Library

  • Sept. 29, 2015, 5:31 a.m.

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  • Jan. 25, 2016, 8:23 p.m.

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Ellis, R. J. PU Disposition in Russian VVERs: Physics Studies of Lead Test Assembly Design, article, May 7, 2000; Tennessee. (digital.library.unt.edu/ark:/67531/metadc724481/: accessed January 23, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.