On using computational versus data-driven methods for uncertainty propagation of isotopic uncertainties-Reference-Cited by-同舟云学术

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On using computational versus data-driven methods for uncertainty propagation of isotopic uncertainties

Published:2020-06 Issue:6 Volume:52 Page:1148-1155
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Radaideh Majdi I.,Price Dean,Kozlowski Tomasz

Funder

U.S. Department of Energy (DOE) through Nuclear Energy University Programs

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference22 articles.

1. Sensitivity and uncertainty analysis of commercial reactor criticals for burnup credit;Radulescu;Nucl. Technol.,2009

2. Propagation of 235,236,238U and 239Pu nuclear data uncertainties for a typical PWR fuel element;Rochman;Nucl. Technol.,2012

3. Criticality safety evaluation of a swiss wet storage pool using a global uncertainty analysis methodology;Pecchia;Ann. Nucl. Energy,2015

4. Monte Carlo burnup and its uncertainty propagation analyses for VERA depletion benchmarks by McCARD;Park;Nucl. Eng. Technol.,2018

5. On the over-conservatism of the 5% depletion uncertainty rule in spent fuel criticality analyses;Metwally;Ann. Nucl. Energy,2019

Cited by 4 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Propagation of radiation source uncertainties in spent fuel cask shielding calculations;Nuclear Engineering and Technology;2022-08

2. Intelligent Basketball Dribble Trajectory Monitoring Based on Data-Driven Technology;Security and Communication Networks;2022-06-22

3. Criticality Analysis for BWR Spent Fuel Based on the Burnup Credit Evaluation from Full Core Simulations;Applied Sciences;2021-02-07

4. Multiphysics Modeling and Validation of Spent Fuel Isotopics Using Coupled Neutronics/Thermal-Hydraulics Simulations;Science and Technology of Nuclear Installations;2020-07-26

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