Reactor Monte Carlo (RMC) model validation and verification in compare with MCNP for plate-type reactor

Mohammad Alrwashdeh; Saeed A. Alameri

doi:10.1063/1.5115807

Reactor Monte Carlo (RMC) model validation and verification in compare with MCNP for plate-type reactor

Mohammad Alrwashdeh, Saeed A. Alameri

Research output: Contribution to journal › Article › peer-review

2 Scopus citations

Abstract

Traditional neutronics calculations and simulation behavior of plate type research reactors pose a challenge comparing with the conventional pressurized water reactors. This is due to its complex geometry, characteristics, heterogeneity, and neutron leakage that lead to modeling difficulties. The Reactor Monte Carlo code (RMC) is employed in stochastic approach for the neutronic analysis in the plate type research reactor. The goal of this report is to examine the capability and validity of the model built using RMC and compare the results with a well-known Monte Carlo code such as MCNP. The results between RMC and MCNP are in a good agreement for effective multiplications factor (k_eff), radial power peaking factor, total power peaking factor, and integral and differential control rods worth.

Original language	British English
Article number	075112
Journal	AIP Advances
Volume	9
Issue number	7
DOIs	https://doi.org/10.1063/1.5115807
State	Published - 1 Jul 2019

Access to Document

10.1063/1.5115807

Cite this

@article{223404bfd05a4cb4bf77f6a50b169046,

title = "Reactor Monte Carlo (RMC) model validation and verification in compare with MCNP for plate-type reactor",

abstract = "Traditional neutronics calculations and simulation behavior of plate type research reactors pose a challenge comparing with the conventional pressurized water reactors. This is due to its complex geometry, characteristics, heterogeneity, and neutron leakage that lead to modeling difficulties. The Reactor Monte Carlo code (RMC) is employed in stochastic approach for the neutronic analysis in the plate type research reactor. The goal of this report is to examine the capability and validity of the model built using RMC and compare the results with a well-known Monte Carlo code such as MCNP. The results between RMC and MCNP are in a good agreement for effective multiplications factor (keff), radial power peaking factor, total power peaking factor, and integral and differential control rods worth.",

author = "Mohammad Alrwashdeh and Alameri, {Saeed A.}",

note = "Funding Information: This study was supported by Khalifa University of Science and Technology Faculty Start-Up Fund, FSU 8474000067. Publisher Copyright: {\textcopyright} 2019 Author(s).",

year = "2019",

month = jul,

day = "1",

doi = "10.1063/1.5115807",

language = "British English",

volume = "9",

journal = "AIP Advances",

issn = "2158-3226",

publisher = "American Institute of Physics",

number = "7",

}

TY - JOUR

T1 - Reactor Monte Carlo (RMC) model validation and verification in compare with MCNP for plate-type reactor

AU - Alrwashdeh, Mohammad

AU - Alameri, Saeed A.

PY - 2019/7/1

Y1 - 2019/7/1

N2 - Traditional neutronics calculations and simulation behavior of plate type research reactors pose a challenge comparing with the conventional pressurized water reactors. This is due to its complex geometry, characteristics, heterogeneity, and neutron leakage that lead to modeling difficulties. The Reactor Monte Carlo code (RMC) is employed in stochastic approach for the neutronic analysis in the plate type research reactor. The goal of this report is to examine the capability and validity of the model built using RMC and compare the results with a well-known Monte Carlo code such as MCNP. The results between RMC and MCNP are in a good agreement for effective multiplications factor (keff), radial power peaking factor, total power peaking factor, and integral and differential control rods worth.

AB - Traditional neutronics calculations and simulation behavior of plate type research reactors pose a challenge comparing with the conventional pressurized water reactors. This is due to its complex geometry, characteristics, heterogeneity, and neutron leakage that lead to modeling difficulties. The Reactor Monte Carlo code (RMC) is employed in stochastic approach for the neutronic analysis in the plate type research reactor. The goal of this report is to examine the capability and validity of the model built using RMC and compare the results with a well-known Monte Carlo code such as MCNP. The results between RMC and MCNP are in a good agreement for effective multiplications factor (keff), radial power peaking factor, total power peaking factor, and integral and differential control rods worth.

UR - http://www.scopus.com/inward/record.url?scp=85069443728&partnerID=8YFLogxK

U2 - 10.1063/1.5115807

DO - 10.1063/1.5115807

M3 - Article

AN - SCOPUS:85069443728

SN - 2158-3226

VL - 9

JO - AIP Advances

JF - AIP Advances

IS - 7

M1 - 075112

ER -

Reactor Monte Carlo (RMC) model validation and verification in compare with MCNP for plate-type reactor

Abstract

Access to Document

Other files and links

Fingerprint

Cite this