skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Conversion of Input Data between KENO and MCNP File Formats for Computer Criticality Assessments

Abstract

KENO is a Monte Carlo criticality code that is maintained by Oak Ridge National Laboratory (ORNL). KENO is included in the SCALE (Standardized Computer Analysis for Licensing Evaluation) package. KENO is often used because it was specifically designed for criticality calculations. Because KENO has convenient geometry input, including the treatment of lattice arrays of materials, it is frequently used for production calculations. Monte Carlo N-Particle (MCNP) is a Monte Carlo transport code maintained by Los Alamos National Laboratory (LANL). MCNP has a powerful 3D geometry package and an extensive cross section database. It is a general-purpose code and may be used for calculations involving shielding or medical facilities, for example, but can also be used for criticality calculations. MCNP is becoming increasingly more popular for performing production criticality calculations. Both codes have their own specific advantages. After a criticality calculation has been performed with one of the codes, it is often desirable (or may be a safety requirement) to repeat the calculation with the other code to compare the important parameters using a different geometry treatment and cross section database. This manual conversion of input files between the two codes is labor intensive. The industry needs the capability of convertingmore » geometry models between MCNP and KENO without a large investment in manpower. The proposed conversion package will aid the user in converting between the codes. It is not intended to be used as a “black box”. The resulting input file will need to be carefully inspected by criticality safety personnel to verify the intent of the calculation is preserved in the conversion. The purpose of this package is to help the criticality specialist in the conversion process by converting the geometry, materials, and pertinent data cards.« less

Authors:
; ;
Publication Date:
Research Org.:
Visual Editor Consultants, Richland, WA
Sponsoring Org.:
USDOE - Office of Nuclear Energy, Science and Technology (NE)
OSTI Identifier:
895741
Report Number(s):
DOE/ER/84178-1
TRN: US0703285
DOE Contract Number:  
FG02-05ER84178
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; 61 RADIATION PROTECTION AND DOSIMETRY; COMPUTERS; CRITICALITY; GEOMETRY; LANL; LICENSING; MANPOWER; ORNL; PRODUCTION; SAFETY; SHIELDING; TRANSPORT; MCNP; KENO; criticality; Monte Carlo

Citation Formats

Schwarz, Randolph A., Carter, Leland L., and Schwarz Alysia L. Conversion of Input Data between KENO and MCNP File Formats for Computer Criticality Assessments. United States: N. p., 2006. Web. doi:10.2172/895741.
Schwarz, Randolph A., Carter, Leland L., & Schwarz Alysia L. Conversion of Input Data between KENO and MCNP File Formats for Computer Criticality Assessments. United States. doi:10.2172/895741.
Schwarz, Randolph A., Carter, Leland L., and Schwarz Alysia L. Thu . "Conversion of Input Data between KENO and MCNP File Formats for Computer Criticality Assessments". United States. doi:10.2172/895741. https://www.osti.gov/servlets/purl/895741.
@article{osti_895741,
title = {Conversion of Input Data between KENO and MCNP File Formats for Computer Criticality Assessments},
author = {Schwarz, Randolph A. and Carter, Leland L. and Schwarz Alysia L.},
abstractNote = {KENO is a Monte Carlo criticality code that is maintained by Oak Ridge National Laboratory (ORNL). KENO is included in the SCALE (Standardized Computer Analysis for Licensing Evaluation) package. KENO is often used because it was specifically designed for criticality calculations. Because KENO has convenient geometry input, including the treatment of lattice arrays of materials, it is frequently used for production calculations. Monte Carlo N-Particle (MCNP) is a Monte Carlo transport code maintained by Los Alamos National Laboratory (LANL). MCNP has a powerful 3D geometry package and an extensive cross section database. It is a general-purpose code and may be used for calculations involving shielding or medical facilities, for example, but can also be used for criticality calculations. MCNP is becoming increasingly more popular for performing production criticality calculations. Both codes have their own specific advantages. After a criticality calculation has been performed with one of the codes, it is often desirable (or may be a safety requirement) to repeat the calculation with the other code to compare the important parameters using a different geometry treatment and cross section database. This manual conversion of input files between the two codes is labor intensive. The industry needs the capability of converting geometry models between MCNP and KENO without a large investment in manpower. The proposed conversion package will aid the user in converting between the codes. It is not intended to be used as a “black box”. The resulting input file will need to be carefully inspected by criticality safety personnel to verify the intent of the calculation is preserved in the conversion. The purpose of this package is to help the criticality specialist in the conversion process by converting the geometry, materials, and pertinent data cards.},
doi = {10.2172/895741},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2006},
month = {11}
}