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Title: MCNP-model for the OAEP Thai Research Reactor

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with the MCNP4B-code to obtain the multiplication factor for the cases with control elements fully inserted, fully withdrawn, and at a working position.
Authors:
; ;
Publication Date:
OSTI Identifier:
677116
Report Number(s):
ORNL/TM--13656
ON: DE99000343; TRN: 99:000993
DOE Contract Number:
AC05-96OR22464
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Jun 1998
Research Org:
Oak Ridge National Lab., TN (United States)
Sponsoring Org:
USDOE Assistant Secretary for Human Resources and Administration, Washington, DC (United States)
Country of Publication:
United States
Language:
English
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; TRR-1 REACTOR; MATHEMATICAL MODELS; REACTOR CORES; MULTIPLICATION FACTORS; CRITICALITY; M CODES; REACTOR LATTICES