New Sampling Method in Continuous Energy Monte Carlo Calculation for Pebble Bed Reactors.

• MURATA Isao

  Department of Nuclear Engineering, Osaka University

• TAKAHASHI Akito

  Department of Nuclear Engineering, Osaka University

• MORI Takamasa

  Japan Atomic Energy Research Institute

• NAKAGAWA Masayuki

  Japan Atomic Energy Research Institute

Bibliographic Information

Other Title

• New Sampling Method in Continuous Energ

Abstract

<BR>A pebble bed reactor generally has double heterogeneity consisting of two kinds of spherical fuel element. In the core, there exist many fuel balls piled up randomly in a high packing fraction. And each fuel ball contains a lot of small fuel particles which are also distributed randomly. In this study, to realize precise neutron transport calculation of such reactors with the continuous energy Monte Carlo method, a new sampling method has been developed. The new method has been implemented in the general purpose Monte Carlo code MCNP to develop a modified version MCNP-BALL. This method was validated by calculating inventory of spherical fuel elements arranged successively by sampling during transport calculation and also by performing criticality calculations in ordered packing models. From the results, it was confirmed that the inventory of spherical fuel elements could be reproduced using MCNP-BALL within a sufficient accuracy of 0.2%. And the comparison of criticality calculations in ordered packing models between MCNP-BALL and the reference method shows excellent agreement in neutron spectrum as well as multiplication factor. <BR>MCNP-BALL enables us to analyze pebble bed type cores such as PROTEUS precisely with the continuous energy Monte Carlo method.

Journal

• Journal of Nuclear Science and Technology

  Journal of Nuclear Science and Technology 34 (8), 734-744, 1997

  Atomic Energy Society of Japan

Keywords

• neutron transport calculation
• computer codes
• accuracy
• errors
• double heterogeneity
• pebble bed reactors
• continuous energy Monte Carlo method
• neutron transport
• HTGR type reactors
• spherical fuel element
• random distribution
• packing simulation
• nearest neighbor distribution

Details

• CRID: 1390282679071715456
• NII Article ID: 10002077663
• NII Book ID: AA00703720
• DOI: 10.3327/jnst.34.734
• COI: 1:CAS:528:DyaK2sXmsVWksr4%3D
• ISSN: 18811248
• ISSN: 00223131
• NDL BIB ID: 4277719
• Web Site: https://ndlsearch.ndl.go.jp/books/R000000004-I4277719
• Text Lang: en
• Data Source:
  • JaLC
  • NDL
  • Crossref
  • CiNii Articles
• Abstract License Flag: Disallowed