Transactions of the American Nuclear Society - Volume 122最新文献_第3页

Modelling of the HTR-PM Pebble-bed Reactor using OpenMC 利用OpenMC对HTR-PM球床反应器进行建模

Transactions of the American Nuclear Society - Volume 122 Pub Date : 2020-06-01 DOI: 10.13182/t31950

B. Forget, D. She, Q. Wang, J. Yu

引用次数: 3

Preliminary Study of Model Predictive Control for Load Follow Operation of Holos Reactor Holos反应堆负荷跟随运行模型预测控制的初步研究

Transactions of the American Nuclear Society - Volume 122 Pub Date : 2020-06-01 DOI: 10.13182/t32327

S. Choi, C. Filippone, S. Kinast, B. Kochunas, V. Şeker

引用次数: 1

Rapid Analytic Determination of Dry Cask Storage Canister Internal Temperatures 干桶储罐内部温度的快速分析测定

Transactions of the American Nuclear Society - Volume 122 Pub Date : 2020-06-01 DOI: 10.13182/t32627

Evan Palmer, Iza Lantgios, Matthew Barry

{"title":"Rapid Analytic Determination of Dry Cask Storage Canister Internal Temperatures","authors":"Evan Palmer, Iza Lantgios, Matthew Barry","doi":"10.13182/t32627","DOIUrl":"https://doi.org/10.13182/t32627","url":null,"abstract":"In the absence of a permanent disposition pathway, the service lifetimes of spent fuel dry cask storage systems (DCS) will likely be longer than originally intended [1]. Due to the still-radioactive nature of the spent fuel, a breach of containment, and the subsequent environmental remediation, would pose a serious hazard to public health. As most canister degradation mechanisms are temperature-dependent, it is essential to develop tools and methods to identify canisters at risk of breach due to prolonged thermal exposure [1].There is currently no expedient method to physically monitor the thermal environment within the DCS. Consequently, a number of studies have modeled temperature profiles of a given DCS configuration with a unique fuel loading exposed to a singular environmental condition using commercially available computational fluid dynamics (CFD) software [2, 3, 4]. Given the large number of individual storage modules, each with a unique fuel activity, the need to predict realistic temperature profiles as a function of time cannot be met through use of CFD modeling due to the computational expense. The purpose of this study is to demonstrate that a low-fidelity, yet robust analytic model can accurately determine these temperate distributions.","PeriodicalId":223521,"journal":{"name":"Transactions of the American Nuclear Society - Volume 122","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129932946","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Multi-physics Coupling of PROTEUS-NODAL and SAM for MSR Simulation under MOOSE Framework MOOSE框架下MSR仿真中proteus - node和SAM的多物理场耦合

Transactions of the American Nuclear Society - Volume 122 Pub Date : 2020-06-01 DOI: 10.13182/t32364

Gang Yang, M. Jaradat, Hansol Park, W. Yang, Changho Lee

引用次数: 2

Cooling Channel Optimization in Additively Manufactured Gas-Cooled Reactor Core 增材制造气冷堆堆芯冷却通道优化

Transactions of the American Nuclear Society - Volume 122 Pub Date : 2020-06-01 DOI: 10.13182/t31977

J. Weinmeister, P. Jain

{"title":"Cooling Channel Optimization in Additively Manufactured Gas-Cooled Reactor Core","authors":"J. Weinmeister, P. Jain","doi":"10.13182/t31977","DOIUrl":"https://doi.org/10.13182/t31977","url":null,"abstract":"New designs for nuclear reactors are now able to take advantage of advanced manufacturing technologies and materials which provide a greater design space for optimization. The Transformational Challenge Reactor (TCR) is designed to demonstrate the revolutionary changes these developments bring to nuclear energy. Current TCR designs are based around a 3 MWth gas-cooled reactor which uses a mixture of traditionally and additively manufactured core components to offer an inherently safe core in a compact size. The TCR fuel forms are manufactured using conventionally fabricated uranium nitride tristructural isotropic (UN TRISO) fuel particles [1] embedded inside an addictively manufactured silicon carbide (SiC) matrix [2]. The fuel forms are first additively manufactured using binderjet printing followed by chemical vapor infiltration [3]. This additively manufactured design is novel compared to previous high temperature gas reactors which heavily rely upon cylindrical cooling channels or pebble bed designs [4]. Unfortunately, engineering software does not yet permit open-ended geometry optimization for thermal fluidic analysis. However, the problem’s mechanics give a few simple constraints that make the problem tractable without eliminating potentially useful designs. This work is focused on constricting the design for detailed optimization work to come while retaining the global optimum. This step is required for the TCR as no comparable design exists to baseline further optimization too. In this summary we first present the problem statement and constraints, then our analysis methods, and finally the results and conclusions of the early optimization work for cooling the TCR, a high temperature gas cooled reactor.","PeriodicalId":223521,"journal":{"name":"Transactions of the American Nuclear Society - Volume 122","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"132183697","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 1

Inverse Depletion of Used Nuclear Fuel: a Bayesian Approach 废核燃料逆向耗竭:贝叶斯方法

Transactions of the American Nuclear Society - Volume 122 Pub Date : 2020-06-01 DOI: 10.13182/t32205

B. Khuwaileh, F. Al-Hamadi, M. Al-Shabi, W. Metwally

引用次数: 0

Unstructured Mesh-Grid Multi-Physics Analysis with Monte Carlo iMC Code for Advanced Fuel Elements 基于蒙特卡罗iMC代码的先进燃料元件非结构网格多物理场分析

Transactions of the American Nuclear Society - Volume 122 Pub Date : 2020-06-01 DOI: 10.13182/t32434

HyeonTae Kim, Yonghee Kim

引用次数: 1

Nuclear Instrumentation and Control Simulation (NICSim) Platform for Investigating Cybersecurity Risks 研究网络安全风险的核仪器与控制仿真(NICSim)平台

Transactions of the American Nuclear Society - Volume 122 Pub Date : 2020-06-01 DOI: 10.13182/t32356

M. El-Genk, T. Schriener

引用次数: 0

Proton Radiation Effects on the Mechanical and Chemical Characteristics of 3D Printed ABS: Preliminary Results 质子辐射对3D打印ABS机械和化学特性的影响:初步结果

Transactions of the American Nuclear Society - Volume 122 Pub Date : 2020-06-01 DOI: 10.13182/t32436

A. Miller, D. Raghavan, G. Warner

引用次数: 1

Radiation Transport with Moving Geometries and Sources Using DAGMC 基于DAGMC的移动几何和源的辐射输运

Transactions of the American Nuclear Society - Volume 122 Pub Date : 2020-06-01 DOI: 10.13182/t32451

Chelsea D'Angelo, P. Wilson

引用次数: 0