Validation Results of Scale and McNp Calculation Codes on Data of Benchmark Critical Experiments at SF-9 Installation

Nuclear Power and the Environment
doi 10.31717/2311-8253.19.1.2
Full Text
Abstract

Available in full text

Date
Authors
Publisher

Institute for Safety Problems of Nuclear Power Plants

Related search

Benchmark Dose Calculation From Epidemiological Data

Biometrics
StatisticsGeneticsProbabilityMolecular BiologyBiochemistryApplied MathematicsMicrobiology ImmunologyBiological SciencesMedicineAgricultural
2001English

Calculation of Multi-Scale, Multi-Loop Integrals Using {\Sf SecDec 3}

Acta Physica Polonica B
AstronomyPhysics
2015English

ZPR-9 Assemblies No. 6-9 Critical Experiments.

1967English

Benchmark Analysis of McNP{trademark} ENDF/B-VI Iron

1994English

Comparison of Results From the McNp™ Criticality Validation Suite Using ENDF/B-VI and Preliminary ENDF/B-VII Nuclear Data

AIP Conference Proceedings
AstronomyPhysics
2005English

Lawrence Livermore Pulsed Sphere Benchmark Analysis of McNP{trademark} ENDF/B-VI

1994English

Physical Models, Cross Sections, and Numerical Approximations Used in McNp and GEANT4 Monte Carlo Codes for Photon and Electron Absorbed Fraction Calculation

Medical Physics
MedicineNuclear MedicineRadiologyImagingBiophysics
2009English

Evaluation of Geometric Progression (GP) Buildup Factors Using McNp Codes (MCNP6.1 and McNp5-1.60)

EPJ Web of Conferences
AstronomyPhysics
2016English

Methodology and Issues of Integral Experiments Selection for Nuclear Data Validation

EPJ Web of Conferences
AstronomyPhysics
2017English

Amanote Research

Note-taking for researchers

Follow Amanote

© 2024 Amaplex Software S.P.R.L. All rights reserved.

Privacy PolicyRefund Policy