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Gamma well-logging in the Old Burial Ground of the Savannah River Site 萨凡纳河遗址老墓地的伽马测井
Transactions of the American Nuclear Society Pub Date : 1995-01-01 DOI: 10.2172/100396
W. G. Winn, K. J. Hofstetter, K. Macmurdo
{"title":"Gamma well-logging in the Old Burial Ground of the Savannah River Site","authors":"W. G. Winn, K. J. Hofstetter, K. Macmurdo","doi":"10.2172/100396","DOIUrl":"https://doi.org/10.2172/100396","url":null,"abstract":"Gamma well-logging measurements were conducted in an inactive, radioactive waste burial ground of the Savannah River Site to appraise whether any evidence existed for downward movement of radioactivity toward the water table. Similar measurements on the same wells were conducted earlier, providing a baseline from which to measure any changes in their radioactive plumes. In particular, the recent measurements sought to detect significant changes in depth location and radiation magnitude of the plumes, as well as the existence of any new plumes. By comparing measurements on a number of these wells, which were distributed on a grid pattern, it was anticipated that the general status of this section of the burial ground could be established.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"122 6 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1995-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88491602","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
Variational estimates of point-kinetics parameters 点动力学参数的变分估计
Transactions of the American Nuclear Society Pub Date : 1994-12-31 DOI: 10.13182/NSE95-A24140
J. Favorite, W. Stacey
{"title":"Variational estimates of point-kinetics parameters","authors":"J. Favorite, W. Stacey","doi":"10.13182/NSE95-A24140","DOIUrl":"https://doi.org/10.13182/NSE95-A24140","url":null,"abstract":"The shortcoming of the conventional piont-kinetics formulation is that it does not treat changes in the neutron flux distribution that may result from core composition changes and feedback. Two light water reactor core models were used in a numerical study to evaluate the variational method for light water reactors.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"3 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1994-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81404086","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: 8
Lessons learned from commercial experience with nuclear plant deactivation to safe storage 从核电站停用到安全储存的商业经验中吸取的教训
Transactions of the American Nuclear Society Pub Date : 1994-12-31 DOI: 10.1016/0140-6701(95)80430-7
S. R. Fischer, T. Sype
{"title":"Lessons learned from commercial experience with nuclear plant deactivation to safe storage","authors":"S. R. Fischer, T. Sype","doi":"10.1016/0140-6701(95)80430-7","DOIUrl":"https://doi.org/10.1016/0140-6701(95)80430-7","url":null,"abstract":"","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"20 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1994-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89667859","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
Management and disposition of excess weapons plutonium 管理和处置多余的武器钚
Transactions of the American Nuclear Society Pub Date : 1994-12-31 DOI: 10.1007/978-94-011-0996-3_8
M. Bunn
{"title":"Management and disposition of excess weapons plutonium","authors":"M. Bunn","doi":"10.1007/978-94-011-0996-3_8","DOIUrl":"https://doi.org/10.1007/978-94-011-0996-3_8","url":null,"abstract":"","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"13 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1994-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77718902","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: 164
The materials dosimetry reference facility 物质剂量测定标准设备
Transactions of the American Nuclear Society Pub Date : 1994-12-31 DOI: 10.1520/STP15134S
A. Hawari, R. Venkataraman, R. Fleming, E. Charles, J. Grundl, E. McGarry
{"title":"The materials dosimetry reference facility","authors":"A. Hawari, R. Venkataraman, R. Fleming, E. Charles, J. Grundl, E. McGarry","doi":"10.1520/STP15134S","DOIUrl":"https://doi.org/10.1520/STP15134S","url":null,"abstract":"A new, high-intensity reference neutron field for reactor dosimetry is in the early stages of operation at the Ford Nuclear Reactor (FNR) at the University of Michigan. Designed and constructed by the National Institute of Standards and Technology (NIST), the facility hosts calibration and validation experiments in support of materials neutron dosimetry for the nuclear power industry and for the metallurgical community engaged in estimating radiation damage in steel. This benchmark is a natural extension of a long-term NIST program to develop standard and reference neutron fields for measurement assurance applications and for testing new detectors and techniques. Field characterization and user operation of the facility is a joint effort by NIST and the Phoenix Memorial Laboratory of the University of Michigan. The materials dosimetry reference facility (NDRF) complements the [sup 235]U cavity fission source at NIST by providing a tenfold increase in fast-neutron fluence, a much larger irradiation volume with modest flux gradients and a neutron spectrum rich in intermediate-energy neutrons. Two spectrum options are available to investigate detector response characteristics and to validate the interpretation of dosimetry measurements.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"14 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1994-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89030728","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
Mixed-oxide fuels testing in the advanced test reactor 混合氧化物燃料在先进试验堆中的试验
Transactions of the American Nuclear Society Pub Date : 1994-12-31 DOI: 10.2172/125351
J. Sterbentz, J. Ryskamp, S. Mason, G. Chang
{"title":"Mixed-oxide fuels testing in the advanced test reactor","authors":"J. Sterbentz, J. Ryskamp, S. Mason, G. Chang","doi":"10.2172/125351","DOIUrl":"https://doi.org/10.2172/125351","url":null,"abstract":"A report recently issued by the National Academy of Sciences describes the need to dispose of 50 metric tons of U.S. weapons-grade plutonium and a similar amount from Russia and makes recommendations for means of disposal. One principal recommendation is to use the plutonium as once-through fuel in existing commercial U.S. light water reactors (LWRs). The report states that a coordinated program of research and development should be undertaken immediately to clarify and resolve the identified technical uncertainties. This paper presents a solution to one needed program: reactor testing of mixed-oxide (MOX) fuels. Currently, weapons-grade plutonium MOX and other types of advanced plutonium-based fuels are being considered as a disposition fuel form. The proposed weapons-grade MOX fuel is unusual, even relative to ongoing foreign experience with reactor-grade MOX power reactor fuel. Some demonstration of the in-reactor thermal, mechanical, and fission gas release behavior of a prototype fuel will most likely be required in a limited number of test reactor irradiations.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"28 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1994-12-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89343896","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
GASFLOW comparisons with bureau of mines experiments GASFLOW与矿务局试验结果的比较
Transactions of the American Nuclear Society Pub Date : 1994-09-01 DOI: 10.2172/10181611
C. Mueller, J. Travis
{"title":"GASFLOW comparisons with bureau of mines experiments","authors":"C. Mueller, J. Travis","doi":"10.2172/10181611","DOIUrl":"https://doi.org/10.2172/10181611","url":null,"abstract":"At the request of the Department of Energy and Westinghouse Hanford Company, the Bureau of Mines has investigated the flammability of mixtures of hydrogen, ammonia, nitrous oxide, and air. The tests were performed in a spherical chamber under quiescent and turbulent conditions. This paper describes combustion calculations using the GASFLOW code and compares the calculated pressure ratios with experiments mentioned above. GASFLOW is a finite-volume computer code that solves the transient, three-dimensional, compressible fluid, Navier-Stokes equations with multiple species coupled with finite-rate chemical kinetics. The computational results show good agreement with the experimental data and confirm GASFLOW to be a valuable tool for evaluating the above combustion process.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"52 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1994-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86542986","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
Preliminary results of a Rossi-alpha experiment on the University of New Mexico`s AGN-201 reactor 新墨西哥大学AGN-201反应堆上罗西α实验的初步结果
Transactions of the American Nuclear Society Pub Date : 1994-07-01 DOI: 10.2172/10163021
R. Busch, G. Spriggs
{"title":"Preliminary results of a Rossi-alpha experiment on the University of New Mexico`s AGN-201 reactor","authors":"R. Busch, G. Spriggs","doi":"10.2172/10163021","DOIUrl":"https://doi.org/10.2172/10163021","url":null,"abstract":"A series of Rossi-alpha measurements was performed on the University of New Mexico`s AGN-201 reactor to measure the effective delayed neutron fraction {beta} and the mean prompt-neutron generation time of the system A{sub m}. An example of one of the Rossi-alpha measurements is shown in Fig. 1. Because the reactor is reflected, multiple prompt-neutron decay modes were observed.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"36 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1994-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87139207","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: 8
Optical and thermophysical properties of high-temperature gaseous uranium for nuclear rocket applications 核火箭用高温气态铀的光学和热物理性质
Transactions of the American Nuclear Society Pub Date : 1994-06-27 DOI: 10.2514/6.1994-2898
V. Banjac, A. Heger
{"title":"Optical and thermophysical properties of high-temperature gaseous uranium for nuclear rocket applications","authors":"V. Banjac, A. Heger","doi":"10.2514/6.1994-2898","DOIUrl":"https://doi.org/10.2514/6.1994-2898","url":null,"abstract":"Research work is currently under way on the design and analysis of advanced gaseous core nuclear rocket concepts. The potentially very high operating temperatures encountered in the gas core nuclear reactor require detailed computational analysis of the fluid dynamics, heat transfer, and neutronics characteristics of such an assembly. Among the most important parameters needed for analysis are the optical and thermophysical properties of the uranium fuel; a detailed set of values is needed as a function of both temperature and pressure to correctly model the conditions that would exist in the gas core reactor.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"54 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1994-06-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80380724","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
Fast shutdown-margin calculation using perturbation theory with regionwise flux expansion 基于区域通量展开的微扰理论快速停机余量计算
Transactions of the American Nuclear Society Pub Date : 1994-03-01 DOI: 10.13182/NSE94-A19812
Jengjung Fang, Y. Liu, Pin-Wu Kao
{"title":"Fast shutdown-margin calculation using perturbation theory with regionwise flux expansion","authors":"Jengjung Fang, Y. Liu, Pin-Wu Kao","doi":"10.13182/NSE94-A19812","DOIUrl":"https://doi.org/10.13182/NSE94-A19812","url":null,"abstract":"Shutdown margin is an important safety parameter in reload core design. In order to search for the most reactive control rod, it is necessary to calculate the worth of each rod, which will require much computing time if three-dimensional full-core calculation is performed. Recently, Smith developed a one-group model for fast shutdown margin calculations in SIMULATE-3. In this paper, a perturbation method with regionwise flux expansion is proposed for fast shutdown-margin calculations. Because it was observed that in cold conditions, with no voids present, the axial distribution of neutron flux will not change drastically when a single control rod is withdrawn from its full-in to full-out position, a two-dimensional model is adopted in this study.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"4 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1994-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81762083","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
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