Published March 2022 | Version v1
Journal article Metadata-only

Calculation of kinetic parameters βeff and Λ with modified open source Monte Carlo code OpenMC(TD)

Creators

  • 1. Comision Chilena de Energía Nuclear, Santiago (Chile)
  • 2. European Spallation Source, Lund (Sweden)
  • 3. IFIC, Paterna (Spain)

Description

This work presents the methodology used to expand the capabilities of the Monte Carlo code OpenMC for the calculation of reactor kinetic parameters: effective delayed neutron fraction βeff and neutron generation time Λ. The modified code, OpenMC(Time-Dependent) or OpenMC(TD), was then used to calculate the effective delayed neutron fraction by using the prompt method, while the neutron generation time was estimated using the pulsed method, fitting Λ to the decay of the neutron population. OpenMC(TD) is intended to serve as an alternative for the estimation of kinetic parameters when licensed codes are not available. The results obtained are compared to experimental data and MCNP calculated values for 18 benchmark configurations

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Technology
Journal Volume
54
Journal Issue
3
Series
16 refs, 2 figs, 5 tabs
Journal Page Range
p. 811-816
ISSN
1738-5733

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
53091668
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Numerical Data
Descriptors DEI
BENCHMARKS; COMPARATIVE EVALUATIONS; CONFIGURATION; COST; DECAY; DELAYED NEUTRON FRACTION; EXPERIMENTAL DATA; LICENSES; MONTE CARLO METHOD; NEUTRONS; POPULATIONS; REACTOR KINETICS; SOCIO-ECONOMIC FACTORS; TIME DEPENDENCE
Descriptors DEC
BARYONS; CALCULATION METHODS; DATA; ELEMENTARY PARTICLES; EVALUATION; FERMIONS; HADRONS; INFORMATION; INSTITUTIONAL FACTORS; KINETICS; NUCLEONS; NUMERICAL DATA