Transactions of the American Nuclear Society最新文献_第7页

Virtual radiation fields for ALARA determination 测定ALARA的虚拟辐射场

Transactions of the American Nuclear Society Pub Date : 1995-12-31 DOI: 10.2172/672123

T. Knight

{"title":"Virtual radiation fields for ALARA determination","authors":"T. Knight","doi":"10.2172/672123","DOIUrl":"https://doi.org/10.2172/672123","url":null,"abstract":"As computing power has increased, so too has the ability to model and simulate complex systems and processes. In addition, virtual reality technology has made it possible to visualize and understand many complex scientific and engineering problems. For this reason, a virtual dosimetry program called Virtual Radiation Fields (VRF) is developed to model radiation dose rate and cumulative dose to a receptor operating in a virtual radiation environment. With the design and testing of many facilities and products taking place in the virtual world, this program facilitates the concurrent consideration of radiological concerns during the design process. Three-dimensional (3D) graphical presentation of the radiation environment is made possible through the use of IGRIP, a graphical modeling program developed by Deneb Robotics, Inc. The VRF simulation program was designed to model and display a virtual dosimeter. As a demonstration of the program`s capability, the Hanford tank, C-106, was modeled to predict radiation doses to robotic equipment used to remove radioactive waste from the tank. To validate VRF dose predictions, comparison was made with reported values for tank C-106, which showed agreement to within 0.5%. Graphical information is presented regarding the 3D dose rate variation inside the tank. Cumulative dose predictions were made for the cleanup operations of tank C-106. A four-dimensional dose rate map generated by VRF was used to model the dose rate not only in 3D space but also as a function of the amount of waste remaining in the tank. This allowed VRF to predict dose rate at any stage in the waste removal process for an accurate simulation of the radiological conditions throughout the tank cleanup procedure.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"26 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1995-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78838459","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: 3

Neutronic analysis of three-element core configurations for the Advanced Neutron Source Reactor 先进中子源堆三元件堆芯结构的中子分析

Transactions of the American Nuclear Society Pub Date : 1995-12-31 DOI: 10.2172/205866

J. Gehin

{"title":"Neutronic analysis of three-element core configurations for the Advanced Neutron Source Reactor","authors":"J. Gehin","doi":"10.2172/205866","DOIUrl":"https://doi.org/10.2172/205866","url":null,"abstract":"The proposed Advanced Neutron Source (ANS) pre-conceptual design consists of a two-element 330 MW{sub f} nuclear reactor fueled with highly-enriched uranium and is cooled, moderated, and reflected with heavy water. Recently, the ANS design has been changed to a three-element configuration in order to permit a reduction of the enrichment, if required, while maintaining or improving the thermal-hydraulic margins. The core consists of three annular fuel elements composed of involute-shaped fuel plates. Each fuel plate has a thickness of 1.27 mm and consists of a fuel meat region Of U{sub 3}Si{sub 2}-Al (50% enriched in one case that was proposed) and an aluminum filler region between aluminum cladding. The individual plates are separated by a 1.27 mm coolant channel. The three element core has a fuel loading of 31 kg of {sup 235}U which is sufficient for a 17-day fuel cycle. The goal in obtaining a new fuel grading is to maximize important temperature margins. The limits imposed axe: (1) Limit the temperature drop over the cladding oxide layer to less than 119{degrees}C to avoid oxide spallation. (2) Limit the fuel centerline temperature to less than 400{degrees}C to avoid fuel damage. (3) Limit the cladding wall temperature to less than the coolant. incipient-boiling temperature to avoid coolant boiling. Other thermal hydraulic conditions, such as critical heat flux, are also considered.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"32 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1995-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89077384","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

Forward-adjoint Monte Carlo coupling with no statistical error propagation 无统计误差传播的前向伴随蒙特卡罗耦合

Transactions of the American Nuclear Society Pub Date : 1995-12-31 DOI: 10.13182/NSE96-A17919

S. N. Cramer

引用次数: 16

Use of sulfur hexafluoride airflow studies to determine the appropriate number and placement of air monitors in an alpha inhalation exposure laboratory 使用六氟化硫气流研究确定α吸入暴露实验室中空气监测仪的适当数量和放置位置

Transactions of the American Nuclear Society Pub Date : 1995-12-01 DOI: 10.2172/381353

G. J. Newton, Hoover

引用次数: 0

PC/FRAM: New capabilities for the gamma-ray spectrometry measurement of plutonium isotopic composition PC/FRAM:用于钚同位素组成的伽马射线光谱测量的新功能

Transactions of the American Nuclear Society Pub Date : 1995-10-01 DOI: 10.2172/114469

T. Sampson, T. Kelley, T. Cremers, T. R. Konkel, R. Friar

引用次数: 6

MOCUP: MCNP-ORIGEN2 coupled utility program MOCUP: MCNP-ORIGEN2耦合实用程序

Transactions of the American Nuclear Society Pub Date : 1995-09-30 DOI: 10.2172/130667

R. Moore, B. Schnitzler, C. Wemple

引用次数: 104

Adjoint ITS calculations using the CEPXS electron-photon cross sections 伴随ITS计算使用CEPXS电子-光子截面

Transactions of the American Nuclear Society Pub Date : 1995-07-01 DOI: 10.2172/90095

L. Lorence, R. Kensek, J. Halbleib

引用次数: 1

Thermal- and ignition-type steam explosions of single drops of molten aluminum 单滴铝液的热式和点火式蒸汽爆炸

Transactions of the American Nuclear Society Pub Date : 1995-07-01 DOI: 10.2172/147716

L. S. Nelson, P. M. Duda, D. Hyndman, D. K. Allison, M. Hyder

{"title":"Thermal- and ignition-type steam explosions of single drops of molten aluminum","authors":"L. S. Nelson, P. M. Duda, D. Hyndman, D. K. Allison, M. Hyder","doi":"10.2172/147716","DOIUrl":"https://doi.org/10.2172/147716","url":null,"abstract":"Seventeen steam explosion experiments were performed with 2 to 10 g drops of molten, high-purity Al. Seven were successfully initiated with underwater exploding bridgewires. At melt release temperatures up to 1400{degrees}C (1673 K) only moderate thermal-type explosions occurred that produced bubbles with volumes up to approximately 1 L. Bubble growth intensified in the melt temperature range 1400-1525{degrees}C (1673--1798 K) as threshold ignition of Al set in. In this range, one of the explosions emitted a flash of light and generated a bubble that grew very rapidly to approximately 14 L, broke through the water surface, and destroyed the test chamber. We attribute the behavior of this latter bubble, which grew as fast as one produced by the underwater firing of a 0.6 g explosive detonator, to an ignition-type steam explosion. Aluminum oxides could not be detected visually in the debris recovered from either typical thermal-type or the ignition-type explosions, and only traces could be detected by X-ray diffraction. In the ignition-type explosion, it is possible however that some oxidic material, probably the smaller particles, was lost during the flooding that occurred as the chamber failed. Both bubble analyses and the absence of appreciable oxide in the debris suggest that themore » ignition-type steam explosion was not very efficient, probably involving the combustion of only a small fraction of the original molten aluminum globule.« less","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"117 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1995-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86815845","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: 6

Development of a risk-based approach to Hanford site cleanup 开发基于风险的汉福德场地清理方法

Transactions of the American Nuclear Society Pub Date : 1995-06-01 DOI: 10.2172/120008

W. Hesser

引用次数: 2

Homogeneous critical Monte Carlo eigenvalue calculations with revised ENDF/B-VI data sets 修正ENDF/B-VI数据集的齐次临界蒙特卡罗特征值计算

Transactions of the American Nuclear Society Pub Date : 1995-04-01 DOI: 10.2172/48679

A. Kahler

引用次数: 2