{"title":"Computational analysis of propagation of geometrical uncertainties to tritium production in FNG WCLL experiment","authors":"Klemen Ambrožič , Gašper Žerovnik , Dieter Leichtle , Maurizio Angelone","doi":"10.1016/j.net.2025.103812","DOIUrl":null,"url":null,"abstract":"<div><div>We present a computational sensitivity and uncertainty analysis of the effect of geometrical uncertainties on the measured reaction rates in the Water Cooled Lithium Lead experimental benchmark, which is a mock-up of a tritium breeding blanket for the future DEMO fusion facility. We used deterministic transport methods to determine the sensitivity of various parts of the geometry and Monte Carlo particle transport methods along with random sampling from geometrical uncertainties, to assess the expected uncertainty and sensitivity profiles, particularly to establish whether tritium self-sufficiency can be achieved within the uncertainty. We have established that most sensitive parts of the geometry are the source position and orientation, as well as the target detector pack position. We have established the uncertainty to be in the range of 8<!--> <!-->% to 25<!--> <!-->%, increasing with the distance from the source. We have also established the sensitivity to the displacement of the target detector pack to be roughly 5<!--> <!-->%<!--> <!-->mm<sup>-1</sup>, while the sensitivity to the perturbation of position of other detector packs and source position and orientation is generally below the 1<!--> <!-->%<!--> <!-->mm<sup>-1</sup>.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 1","pages":"Article 103812"},"PeriodicalIF":2.6000,"publicationDate":"2025-08-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Technology","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S1738573325003808","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
We present a computational sensitivity and uncertainty analysis of the effect of geometrical uncertainties on the measured reaction rates in the Water Cooled Lithium Lead experimental benchmark, which is a mock-up of a tritium breeding blanket for the future DEMO fusion facility. We used deterministic transport methods to determine the sensitivity of various parts of the geometry and Monte Carlo particle transport methods along with random sampling from geometrical uncertainties, to assess the expected uncertainty and sensitivity profiles, particularly to establish whether tritium self-sufficiency can be achieved within the uncertainty. We have established that most sensitive parts of the geometry are the source position and orientation, as well as the target detector pack position. We have established the uncertainty to be in the range of 8 % to 25 %, increasing with the distance from the source. We have also established the sensitivity to the displacement of the target detector pack to be roughly 5 % mm-1, while the sensitivity to the perturbation of position of other detector packs and source position and orientation is generally below the 1 % mm-1.
期刊介绍:
Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters.
NET covers all fields for peaceful utilization of nuclear energy and radiation as follows:
1) Reactor Physics
2) Thermal Hydraulics
3) Nuclear Safety
4) Nuclear I&C
5) Nuclear Physics, Fusion, and Laser Technology
6) Nuclear Fuel Cycle and Radioactive Waste Management
7) Nuclear Fuel and Reactor Materials
8) Radiation Application
9) Radiation Protection
10) Nuclear Structural Analysis and Plant Management & Maintenance
11) Nuclear Policy, Economics, and Human Resource Development