Evaluation of Kinetic Parameters RSG-GAS Reactor Equilibrium Silicide Core Using Continuous-Energy Monte Carlo Serpent 2 Code

Surian Pinem; Liem Peng Hong; Wahid Luthfi; Tukiran Surbakti; Donny Hartanto

doi:10.1080/00295639.2023.2284433

Evaluation of Kinetic Parameters RSG-GAS Reactor Equilibrium Silicide Core Using Continuous-Energy Monte Carlo Serpent 2 Code

Surian Pinem
, Liem Peng Hong
, Wahid Luthfi
, Tukiran Surbakti
, Donny Hartanto

Reactor and Nuclear Fuel Cycle Analysis

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

2 Scopus citations

Abstract

The purpose of this study is to determine the kinetic parameters of the RSG-GAS equilibrium core. The calculated kinetic parameters are the effective delayed neutron fraction β_eff, the neutron generation time Ʌ, and the prompt neutron lifetime ℓ since they are related to the safety of nuclear operations. The kinetic parameters were calculated using the Serpent 2 code with the ENDF/B-VII.1 and ENDF/B-VIII.0 nuclear data libraries. Calculations were performed using various adjoint-weighted methods such as Meulekamp’s method, Nauchi’s method, the Iterated Fission Probability method, and the Perturbation Technique. The calculated results of the six-group delayed neutron fraction by the Meulekamp and the IFP methods showed no significant difference. Choosing the IFP method as the reference, the maximum difference for β_eff (694 pcm) is 0.73%, and the maximum difference for Ʌ and ℓ is 1.89%. The calculated kinetic parameters with ENDF/B-VII.1 and ENDF/B-VIII.0 are quite close, with a maximum difference of 0.9%. The sensitivity analysis results indicate several nuclides and reaction types that dominantly affect the β_eff and Λ. The results of the kinetic parameter calculations can be used for the safety analysis of the RSG-GAS equilibrium core.

Original language	English
Pages (from-to)	1935-1949
Number of pages	15
Journal	Nuclear Science and Engineering
Volume	198
Issue number	10
DOIs	https://doi.org/10.1080/00295639.2023.2284433
State	Published - 2024

Funding

This research has been supported by BRIN Indonesia through Rumah Progam Hasil Inovasi Teknologi Nuklir (RP HITN) - Program House for Nuclear Technology Innovation on fiscal year 2022 number B-277/V/TN/4/2022 with its budget came from DIPA-124.01.1.690503/2022. Thanks are due the head of the Research Center for Nuclear Reactor Technology (PRTRN) Research Organization for Nuclear Energy (ORTN) National Research and Innovation Agency (BRIN) for supporting this research through DIPA 2022. Also Thanks for the support of Department of Mechanical and Nuclear Engineering of the University of Sharjah, United Arab Emirates.

Keywords

ENDF/B-VII.1
ENDF/B-VIII.0
Kinetic parameters
RSG-GAS
Serpent 2
equilibrium core

Access to Document

10.1080/00295639.2023.2284433

Cite this

@article{26825e3266e0459283039ddae90f99a2,

title = "Evaluation of Kinetic Parameters RSG-GAS Reactor Equilibrium Silicide Core Using Continuous-Energy Monte Carlo Serpent 2 Code",

abstract = "The purpose of this study is to determine the kinetic parameters of the RSG-GAS equilibrium core. The calculated kinetic parameters are the effective delayed neutron fraction βeff, the neutron generation time Ʌ, and the prompt neutron lifetime ℓ since they are related to the safety of nuclear operations. The kinetic parameters were calculated using the Serpent 2 code with the ENDF/B-VII.1 and ENDF/B-VIII.0 nuclear data libraries. Calculations were performed using various adjoint-weighted methods such as Meulekamp{\textquoteright}s method, Nauchi{\textquoteright}s method, the Iterated Fission Probability method, and the Perturbation Technique. The calculated results of the six-group delayed neutron fraction by the Meulekamp and the IFP methods showed no significant difference. Choosing the IFP method as the reference, the maximum difference for βeff (694 pcm) is 0.73\%, and the maximum difference for Ʌ and ℓ is 1.89\%. The calculated kinetic parameters with ENDF/B-VII.1 and ENDF/B-VIII.0 are quite close, with a maximum difference of 0.9\%. The sensitivity analysis results indicate several nuclides and reaction types that dominantly affect the βeff and Λ. The results of the kinetic parameter calculations can be used for the safety analysis of the RSG-GAS equilibrium core.",

keywords = "ENDF/B-VII.1, ENDF/B-VIII.0, Kinetic parameters, RSG-GAS, Serpent 2, equilibrium core",

author = "Surian Pinem and Hong, \{Liem Peng\} and Wahid Luthfi and Tukiran Surbakti and Donny Hartanto",

note = "Publisher Copyright: {\textcopyright} 2024 American Nuclear Society.",

year = "2024",

doi = "10.1080/00295639.2023.2284433",

language = "English",

volume = "198",

pages = "1935--1949",

journal = "Nuclear Science and Engineering",

issn = "0029-5639",

publisher = "Taylor and Francis Group",

number = "10",

}

TY - JOUR

T1 - Evaluation of Kinetic Parameters RSG-GAS Reactor Equilibrium Silicide Core Using Continuous-Energy Monte Carlo Serpent 2 Code

AU - Pinem, Surian

AU - Hong, Liem Peng

AU - Luthfi, Wahid

AU - Surbakti, Tukiran

AU - Hartanto, Donny

PY - 2024

Y1 - 2024

N2 - The purpose of this study is to determine the kinetic parameters of the RSG-GAS equilibrium core. The calculated kinetic parameters are the effective delayed neutron fraction βeff, the neutron generation time Ʌ, and the prompt neutron lifetime ℓ since they are related to the safety of nuclear operations. The kinetic parameters were calculated using the Serpent 2 code with the ENDF/B-VII.1 and ENDF/B-VIII.0 nuclear data libraries. Calculations were performed using various adjoint-weighted methods such as Meulekamp’s method, Nauchi’s method, the Iterated Fission Probability method, and the Perturbation Technique. The calculated results of the six-group delayed neutron fraction by the Meulekamp and the IFP methods showed no significant difference. Choosing the IFP method as the reference, the maximum difference for βeff (694 pcm) is 0.73%, and the maximum difference for Ʌ and ℓ is 1.89%. The calculated kinetic parameters with ENDF/B-VII.1 and ENDF/B-VIII.0 are quite close, with a maximum difference of 0.9%. The sensitivity analysis results indicate several nuclides and reaction types that dominantly affect the βeff and Λ. The results of the kinetic parameter calculations can be used for the safety analysis of the RSG-GAS equilibrium core.

AB - The purpose of this study is to determine the kinetic parameters of the RSG-GAS equilibrium core. The calculated kinetic parameters are the effective delayed neutron fraction βeff, the neutron generation time Ʌ, and the prompt neutron lifetime ℓ since they are related to the safety of nuclear operations. The kinetic parameters were calculated using the Serpent 2 code with the ENDF/B-VII.1 and ENDF/B-VIII.0 nuclear data libraries. Calculations were performed using various adjoint-weighted methods such as Meulekamp’s method, Nauchi’s method, the Iterated Fission Probability method, and the Perturbation Technique. The calculated results of the six-group delayed neutron fraction by the Meulekamp and the IFP methods showed no significant difference. Choosing the IFP method as the reference, the maximum difference for βeff (694 pcm) is 0.73%, and the maximum difference for Ʌ and ℓ is 1.89%. The calculated kinetic parameters with ENDF/B-VII.1 and ENDF/B-VIII.0 are quite close, with a maximum difference of 0.9%. The sensitivity analysis results indicate several nuclides and reaction types that dominantly affect the βeff and Λ. The results of the kinetic parameter calculations can be used for the safety analysis of the RSG-GAS equilibrium core.

KW - ENDF/B-VII.1

KW - ENDF/B-VIII.0

KW - Kinetic parameters

KW - RSG-GAS

KW - Serpent 2

KW - equilibrium core

UR - https://www.scopus.com/pages/publications/85183029068

U2 - 10.1080/00295639.2023.2284433

DO - 10.1080/00295639.2023.2284433

M3 - Article

AN - SCOPUS:85183029068

SN - 0029-5639

VL - 198

SP - 1935

EP - 1949

JO - Nuclear Science and Engineering

JF - Nuclear Science and Engineering

IS - 10

ER -

Evaluation of Kinetic Parameters RSG-GAS Reactor Equilibrium Silicide Core Using Continuous-Energy Monte Carlo Serpent 2 Code

Abstract

Funding

Keywords

Access to Document

Other files and links

Fingerprint

Cite this