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TSUNAMI Primer: A Primer for Sensitivity/Uncertainty Calculations with SCALE

https://doi.org/10.2172/947598
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What this work says

Outgoing claims: the papers this work cites, builds on, or argues with.

inferredcites →https://doi.org/10.13182/nse03-2openalex-snapshot
Sensitivity- and Uncertainty-Based Criticality Safety Validation Techniques
inferredcites →https://doi.org/10.2172/469122openalex-snapshot
Criticality benchmark guide for light-water-reactor fuel in transportation and storage packages
inferredcites →https://doi.org/10.2172/469126openalex-snapshot
SCALE: A modular code system for performing standardized computer analyses for licensing evaluation
inferredcites →https://doi.org/10.2172/950002openalex-snapshot
Application of the SCALE TSUNAMI Tools for the Validation of Criticality Safety Calculations Involving 233U
inferredcites →https://doi.org/10.2307/2284752openalex-snapshot
Data Reduction and Error Analysis for the Physical Sciences.

What points at this work

Incoming claims: where this work appears in other papers’ reference lists and arguments.

inferred← citeshttps://doi.org/10.2139/ssrn.4801241openalex-extracted
Applicability Domain and Gaps of Snf Decay Heat Validation Data – Similarity-Based Approach
inferred← citeshttps://doi.org/10.1016/j.anucene.2011.06.014openalex-snapshot
Modeling and criticality evaluation of the voloxidation process
inferred← citeshttps://doi.org/10.1016/j.anucene.2014.11.019openalex-snapshot
Verification of the new implementations in SHARKX against TSUNAMI to perform pinpower UQ and representativity analysis
inferred← citeshttps://doi.org/10.1016/j.anucene.2015.12.035openalex-snapshot
Uncertainty quantification and representativity analysis of LWR-PROTEUS Phase III experiments using SHARKX
inferred← citeshttps://doi.org/10.1016/j.anucene.2024.110905openalex-snapshot
Applicability domain and gaps of SNF decay heat validation data – A similarity-based approach
inferred← citeshttps://doi.org/10.1016/j.nds.2017.01.001openalex-snapshot
Nuclear Data Uncertainties for Typical LWR Fuel Assemblies and a Simple Reactor Core
inferred← citeshttps://doi.org/10.1016/j.net.2020.07.012openalex-snapshot
Uncertainty quantification of PWR spent fuel due to nuclear data and modeling parameters
inferred← citeshttps://doi.org/10.1038/s41598-023-32112-7openalex-snapshot
Stochastic gradient descent for optimization for nuclear systems
inferred← citeshttps://doi.org/10.1051/epjconf/202124710033openalex-snapshot
NEUTRONIC BENCHMARKING OF SMALL GAS-COOLED SYSTEMS
inferred← citeshttps://doi.org/10.1080/00295450.2021.1938910openalex-snapshot
Calculated Critical and Subcritical Data for Revision of ANSI/ANS 8.12
inferred← citeshttps://doi.org/10.1080/18811248.2011.9711778openalex-snapshot
Criticality Safety Evaluation of Materials Concerning Pyroprocessing
inferred← citeshttps://doi.org/10.1115/1.4066404openalex-snapshot
TSUNAMI Analyses of the Similarity and Applicability of Zero Energy Deuterium 2 Critical Experiments for Reactor Physics Code Benchmarking for a Pressurized Water Reactor Small Modular Reactor Design Concept
inferred← citeshttps://doi.org/10.21608/ajnsa.2022.172466.1668openalex-snapshot
Control Rod Worth Uncertainty Propagation from Nuclear Data for NUR Research Reactor
inferred← citeshttps://doi.org/10.2172/985288openalex-snapshot
Getting Started with VIBE as a DICE Plug-in Module
inferred← citeshttps://doi.org/10.34917/9112096openalex-snapshot
MCNP6 Computational-Based Sensitivity Propagation Analysis of Continuous Neutron Cross-Sections Using the Godiva (HMF-001) and the Godiver (HMF-004) Benchmark Criticality Study Cases
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