MCNP-model for the OAEP Thai Research Reactor

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Description

An MCNP input was prepared for the Thai Research Reactor, making extensive use of the MCNP geometry`s lattice feature that allows a flexible and easy rearrangement of the core components and the adjustment of the control elements. The geometry was checked for overdefined or undefined zones by two-dimensional plots of cuts through the core configuration with the MCNP geometry plotting capabilities, and by a three-dimensional view of the core configuration with the SABRINA code. Cross sections were defined for a hypothetical core of 67 standard fuel elements and 38 low-enriched uranium fuel elements--all filled with fresh fuel. Three test calculations ... continued below

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41 p.

Creation Information

Gallmeier, F.X.; Tang, J.S. & Primm, R.T. III June 1, 1998.

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Description

An MCNP input was prepared for the Thai Research Reactor, making extensive use of the MCNP geometry`s lattice feature that allows a flexible and easy rearrangement of the core components and the adjustment of the control elements. The geometry was checked for overdefined or undefined zones by two-dimensional plots of cuts through the core configuration with the MCNP geometry plotting capabilities, and by a three-dimensional view of the core configuration with the SABRINA code. Cross sections were defined for a hypothetical core of 67 standard fuel elements and 38 low-enriched uranium fuel elements--all filled with fresh fuel. Three test calculations were performed with the MCNP4B-code to obtain the multiplication factor for the cases with control elements fully inserted, fully withdrawn, and at a working position.

Physical Description

41 p.

Notes

INIS; OSTI as DE99000343

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  • Other Information: PBD: Jun 1998

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  • Other: DE99000343
  • Report No.: ORNL/TM--13656
  • Grant Number: AC05-96OR22464
  • DOI: 10.2172/677116 | External Link
  • Office of Scientific & Technical Information Report Number: 677116
  • Archival Resource Key: ark:/67531/metadc703416

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Office of Scientific & Technical Information Technical Reports

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Creation Date

  • June 1, 1998

Added to The UNT Digital Library

  • Sept. 12, 2015, 6:31 a.m.

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  • May 20, 2016, 2:56 p.m.

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Gallmeier, F.X.; Tang, J.S. & Primm, R.T. III. MCNP-model for the OAEP Thai Research Reactor, report, June 1, 1998; Tennessee. (digital.library.unt.edu/ark:/67531/metadc703416/: accessed December 14, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.