The Nuclear Regulatory Commission requires utilities to determine the response of a pressurized water reactor to a steam generator tube rupture (SGTR) as part of the safety analysis for the plant. The SGTR analysis includes assumptions regarding the iodine concentration in the reactor coolant system (RCS) due to iodine spikes, primary flashing and bypass fractions, and iodine partitioning in the secondary coolant system (SCS). Experimental and analytical investigations have recently been completed wherein these assumptions were tested to determine whether and to what degree they were conservative (that is, whether they result in a calculated iodine source term/dose that is at least as large or larger than that expected during an actual event). The current study has the objective to assess the overall effects of the results of these investigations on the calculated iodine dose to the environment during an SGTR. To assist in this study, a computer program, DOSE, was written. This program uses a simple, non-mechanistic model to calculate the iodine source term to the environment during an SGTR as a function of water mass inventories and flow rates and iodine concentrations in the RCS and SCS. The principal conclusion of this study is that the iodine concentrationmore » in the RCS is the dominant parameter, due to the dominance of primary flashing on the iodine source term.« less
{"title":"Assessment of dose during an SGTR","authors":"J. Adams","doi":"10.2172/10145930","DOIUrl":"https://doi.org/10.2172/10145930","url":null,"abstract":"The Nuclear Regulatory Commission requires utilities to determine the response of a pressurized water reactor to a steam generator tube rupture (SGTR) as part of the safety analysis for the plant. The SGTR analysis includes assumptions regarding the iodine concentration in the reactor coolant system (RCS) due to iodine spikes, primary flashing and bypass fractions, and iodine partitioning in the secondary coolant system (SCS). Experimental and analytical investigations have recently been completed wherein these assumptions were tested to determine whether and to what degree they were conservative (that is, whether they result in a calculated iodine source term/dose that is at least as large or larger than that expected during an actual event). The current study has the objective to assess the overall effects of the results of these investigations on the calculated iodine dose to the environment during an SGTR. To assist in this study, a computer program, DOSE, was written. This program uses a simple, non-mechanistic model to calculate the iodine source term to the environment during an SGTR as a function of water mass inventories and flow rates and iodine concentrations in the RCS and SCS. The principal conclusion of this study is that the iodine concentrationmore » in the RCS is the dominant parameter, due to the dominance of primary flashing on the iodine source term.« less","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"96 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1993-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84606243","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}
From the beginning at Los Alamos National Laboratory (LANL), solutions to the transport equation were very important. Many long-forgotten approximate solution techniques, including one by Feynman, were developed to help design nuclear weapons. Most of these methods were based on the methods of mathematical physics familiar to the project physicists and predated the use of computers, but continued research and pressing need produced two new and powerful computer-based systems: Monte Carlo and the S[sub N] method. The healthy and long-term competition between the two LANL groups responsible for these quite different approaches was both stimulating and synergistic.
从洛斯阿拉莫斯国家实验室(Los Alamos National Laboratory, LANL)开始，输运方程的解就非常重要。许多长期被遗忘的近似解技术，包括费曼的一种，都是为了帮助设计核武器而开发的。这些方法大多是基于项目物理学家熟悉的数学物理方法，并且早于计算机的使用，但持续的研究和迫切的需求产生了两个新的强大的基于计算机的系统:蒙特卡罗和S[sub N]方法。负责这些截然不同的方法的两个LANL集团之间健康和长期的竞争既刺激又协同。
{"title":"The early days of the S{sub n} method","authors":"K. D. Lathrop","doi":"10.2172/10149264","DOIUrl":"https://doi.org/10.2172/10149264","url":null,"abstract":"From the beginning at Los Alamos National Laboratory (LANL), solutions to the transport equation were very important. Many long-forgotten approximate solution techniques, including one by Feynman, were developed to help design nuclear weapons. Most of these methods were based on the methods of mathematical physics familiar to the project physicists and predated the use of computers, but continued research and pressing need produced two new and powerful computer-based systems: Monte Carlo and the S[sub N] method. The healthy and long-term competition between the two LANL groups responsible for these quite different approaches was both stimulating and synergistic.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"59 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1992-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83932788","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}
R. Gehrke, M. Putnam, S. G. Goodwin, R. L. Kynaston
A technique has been developed to rapidly measure the presence of plutonium in soils, filters, smears, and glass waste forms by measuring the uranium L-shell x-ray emissions associated with the decay of plutonium. In addition, the technique can simultaneously acquire spectra of samples and automatically analyze them for the amount of americium, and gamma-ray emitting activation and fission products present. The samples are counted with a large area, thin-window, n-type Ge spectrometer which is equally efficient for the detection of low energy x-rays (>10 key), as well as high-energy gamma rays (>1 MeV). A 8192-channel analyzer is used to acquire the entire photon spectrum at one time. A dual-energy, time-tagged pulser, that is injected into the test input of the preamplifier to monitor the energy scale, detector resolution, and pulse pile-up will be installed in FY-92. The L x-ray portion of each spectrum is analyzed by a linear least-squares spectral fitting technique originally developed for the analysis of spectra from NaI(Tl) detectors. The gamma-ray portion of each spectrum is analyzed by a standard Ge gamma-ray analysis package. Detection limits (also referred to as lower limits of detection) for plutonium in contaminated soils that have been achieved by this technique aremore » reported.« less
{"title":"Rapid assay of plutonium in soils by passive L x-ray counting","authors":"R. Gehrke, M. Putnam, S. G. Goodwin, R. L. Kynaston","doi":"10.2172/10163234","DOIUrl":"https://doi.org/10.2172/10163234","url":null,"abstract":"A technique has been developed to rapidly measure the presence of plutonium in soils, filters, smears, and glass waste forms by measuring the uranium L-shell x-ray emissions associated with the decay of plutonium. In addition, the technique can simultaneously acquire spectra of samples and automatically analyze them for the amount of americium, and gamma-ray emitting activation and fission products present. The samples are counted with a large area, thin-window, n-type Ge spectrometer which is equally efficient for the detection of low energy x-rays (>10 key), as well as high-energy gamma rays (>1 MeV). A 8192-channel analyzer is used to acquire the entire photon spectrum at one time. A dual-energy, time-tagged pulser, that is injected into the test input of the preamplifier to monitor the energy scale, detector resolution, and pulse pile-up will be installed in FY-92. The L x-ray portion of each spectrum is analyzed by a linear least-squares spectral fitting technique originally developed for the analysis of spectra from NaI(Tl) detectors. The gamma-ray portion of each spectrum is analyzed by a standard Ge gamma-ray analysis package. Detection limits (also referred to as lower limits of detection) for plutonium in contaminated soils that have been achieved by this technique aremore » reported.« less","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"8 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1992-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73476841","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}
D. Sire, C. Bendixsen, E. Armstrong, R. Henry, G. B. Frandsen
The U.S. Department of Energy (DOE) is the owner of, or has on consignment, a large quantity of nuclear fuel and targets from a variety of nuclear reactors. The majority of this inventory is associated with the nuclear materials production (NMP) complex. This material must be disposed in a safe an controlled manner. The special Fuels Canning and Characterization Facility (SFCCF) is required to characterize, verify the storage can contents, and, if necessary, recan the special fuels to help ensure safe, interim storage (i.e. fission product containment and criticality control) until a special fuels disposal facility is operating, regardless of which disposal technique is adopted. The SFCCF would be located at the Idaho Chemical Processing Plant (ICPP) and would include the capability to condition the special fuels in preparation for final disposal.
{"title":"ICPP special fuels canning and characterization facility","authors":"D. Sire, C. Bendixsen, E. Armstrong, R. Henry, G. B. Frandsen","doi":"10.2172/10157267","DOIUrl":"https://doi.org/10.2172/10157267","url":null,"abstract":"The U.S. Department of Energy (DOE) is the owner of, or has on consignment, a large quantity of nuclear fuel and targets from a variety of nuclear reactors. The majority of this inventory is associated with the nuclear materials production (NMP) complex. This material must be disposed in a safe an controlled manner. The special Fuels Canning and Characterization Facility (SFCCF) is required to characterize, verify the storage can contents, and, if necessary, recan the special fuels to help ensure safe, interim storage (i.e. fission product containment and criticality control) until a special fuels disposal facility is operating, regardless of which disposal technique is adopted. The SFCCF would be located at the Idaho Chemical Processing Plant (ICPP) and would include the capability to condition the special fuels in preparation for final disposal.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"7 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1992-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81605346","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}
Not every student is meant to be a scientist. Students come into a classroom with a variety of experiences, interests, and abilities. Therefore, the goal of any science program is not the production of chemists, physicists, or biologists but the development of scientifically literature individuals: students who can question, hypothesize, test, record, and conclude. The classroom environment cannot always provide the range of real-life experiences necessary for students to internalize the scientific method. The Illinois Junior Academy of Science (IJAS), through its sponsorship of local, regional, and state science fair competitions, seeks to assist the schools by providing just such practical hands-on experiences. The IJAS-sponsored expositions allow students the opportunity to translate classroom knowledge into a form that is tangible and concrete, an event that goes beyond the walls of a classroom into the reality of the world in which they will live and work.
{"title":"Science beyond the classroom","authors":"J. Petric, J. Bonkalski","doi":"10.2505/9781933531373","DOIUrl":"https://doi.org/10.2505/9781933531373","url":null,"abstract":"Not every student is meant to be a scientist. Students come into a classroom with a variety of experiences, interests, and abilities. Therefore, the goal of any science program is not the production of chemists, physicists, or biologists but the development of scientifically literature individuals: students who can question, hypothesize, test, record, and conclude. The classroom environment cannot always provide the range of real-life experiences necessary for students to internalize the scientific method. The Illinois Junior Academy of Science (IJAS), through its sponsorship of local, regional, and state science fair competitions, seeks to assist the schools by providing just such practical hands-on experiences. The IJAS-sponsored expositions allow students the opportunity to translate classroom knowledge into a form that is tangible and concrete, an event that goes beyond the walls of a classroom into the reality of the world in which they will live and work.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"132 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1992-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74224402","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}
Thermal testing of cadmium safety rods was conducted as part of a program to define the response of Savannah River Site (SRS) production reactor core components to a hypothetical LOCA leading to a drained reactor tank. The safety rods are present in the reactor core only during shutdown and are not used as a control mechanism during operation; thus, their response to the conditions predicted for the LOCA is only of interest to the extent that it could impact the progression of the accident. This document provides a description of this testing.
{"title":"Cadmium safety rod thermal tests","authors":"J. K. Thomas, N. C. Iyer, H. Peacock","doi":"10.2172/5458924","DOIUrl":"https://doi.org/10.2172/5458924","url":null,"abstract":"Thermal testing of cadmium safety rods was conducted as part of a program to define the response of Savannah River Site (SRS) production reactor core components to a hypothetical LOCA leading to a drained reactor tank. The safety rods are present in the reactor core only during shutdown and are not used as a control mechanism during operation; thus, their response to the conditions predicted for the LOCA is only of interest to the extent that it could impact the progression of the accident. This document provides a description of this testing.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"78 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1992-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84019430","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}
Pub Date : 1992-01-01DOI: 10.1201/9781482273168-49
K. Morehouse
A reliable method is needed to determine if foods have been irradiated and are in compliance with respect to the allowable absorbed radiation dose. Several approaches for the identification of irradiated foods are under development worldwide. These include measurement of o-tyrosine, radiolytically generated hydrocarbons from lipids and chemiluminescence or thermoluminescence, and the use of electron spin resonance (ESR) to measure free radicals trapped in calcified tissues. This paper describes the efforts being undertaken at the FDA to develop analytical procedures to monitor and identify foods that have been treated with ionizing radiation. In particular, it focuses on the use of an ESR approach to measure radiation-induced free radicals trapped in calcified tissues and the use of a capillary gas chromatography (GC)-based procedure to determine radiolytically generated hydrocarbons formed by the radiolysis of lipids in various foods.
{"title":"Identification of irradiated foods","authors":"K. Morehouse","doi":"10.1201/9781482273168-49","DOIUrl":"https://doi.org/10.1201/9781482273168-49","url":null,"abstract":"A reliable method is needed to determine if foods have been irradiated and are in compliance with respect to the allowable absorbed radiation dose. Several approaches for the identification of irradiated foods are under development worldwide. These include measurement of o-tyrosine, radiolytically generated hydrocarbons from lipids and chemiluminescence or thermoluminescence, and the use of electron spin resonance (ESR) to measure free radicals trapped in calcified tissues. This paper describes the efforts being undertaken at the FDA to develop analytical procedures to monitor and identify foods that have been treated with ionizing radiation. In particular, it focuses on the use of an ESR approach to measure radiation-induced free radicals trapped in calcified tissues and the use of a capillary gas chromatography (GC)-based procedure to determine radiolytically generated hydrocarbons formed by the radiolysis of lipids in various foods.","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"9 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1992-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88623438","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}
J. Hirschfelder, P. Chambré, W.W.-L. Lee, T. Pigford, M. Sadeghi
Partitioning the actinides in spent fuel and transmuting them in actinide-burning liquid-metal reactors (ALMRs) is a potential method of reducing public risks from the geologic disposal of nuclear waste. In this paper, the authors present a comparison of radionuclide releases from burial at Yucca Mountain of spent fuel and of ALMR wastes. Two waste disposal schemes are considered. In each, the heat generation of the wastes at emplacement is 9.88 {times} 10{sup 7} W, the maximum for the repository. In the first scheme, the repository contains 86,700 tonnes of initial heavy metal (IHM) of light water reactor (LWR) spent fuel. In the second scheme, all current LWRs operate for a 40-yr lifetime, producing a total of 84,000 tonnes IHM of spent fuel. This spent fuel is treated using a pyrochemical process in which 98.4% of the uranium and 99.8% of the neptunium, plutonium, americium, and curium are extracted and fabricated into ALMR fuel, with the reprocessing wastes destined for the repository. The ALMR requires this fuel for its startup and first two reloads; thereafter, it is self-sufficient. Spent ALMR fuel is also pyrochemically reprocessed: 99.9% of the transuranics is recovered and recycled into ALMR fuel, and the wastes are placedmore » in the repository. Thus, in the second scheme, the repository contains the wastes from reprocessing all of the LWR spent fuel plus the maximum amount of ALMR reprocessing wastes allowed in the repository based on its heat generation limit.« less
{"title":"Effects of actinide burning on waste disposal at Yucca Mountain","authors":"J. Hirschfelder, P. Chambré, W.W.-L. Lee, T. Pigford, M. Sadeghi","doi":"10.2172/140748","DOIUrl":"https://doi.org/10.2172/140748","url":null,"abstract":"Partitioning the actinides in spent fuel and transmuting them in actinide-burning liquid-metal reactors (ALMRs) is a potential method of reducing public risks from the geologic disposal of nuclear waste. In this paper, the authors present a comparison of radionuclide releases from burial at Yucca Mountain of spent fuel and of ALMR wastes. Two waste disposal schemes are considered. In each, the heat generation of the wastes at emplacement is 9.88 {times} 10{sup 7} W, the maximum for the repository. In the first scheme, the repository contains 86,700 tonnes of initial heavy metal (IHM) of light water reactor (LWR) spent fuel. In the second scheme, all current LWRs operate for a 40-yr lifetime, producing a total of 84,000 tonnes IHM of spent fuel. This spent fuel is treated using a pyrochemical process in which 98.4% of the uranium and 99.8% of the neptunium, plutonium, americium, and curium are extracted and fabricated into ALMR fuel, with the reprocessing wastes destined for the repository. The ALMR requires this fuel for its startup and first two reloads; thereafter, it is self-sufficient. Spent ALMR fuel is also pyrochemically reprocessed: 99.9% of the transuranics is recovered and recycled into ALMR fuel, and the wastes are placedmore » in the repository. Thus, in the second scheme, the repository contains the wastes from reprocessing all of the LWR spent fuel plus the maximum amount of ALMR reprocessing wastes allowed in the repository based on its heat generation limit.« less","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"46 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1991-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74192667","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}
Pub Date : 1991-01-01DOI: 10.1016/0148-9062(91)93690-8
T. Schultheis, S. Pickering, S. Orrell
{"title":"In situ testing program at the Waste Isolation Pilot Plant","authors":"T. Schultheis, S. Pickering, S. Orrell","doi":"10.1016/0148-9062(91)93690-8","DOIUrl":"https://doi.org/10.1016/0148-9062(91)93690-8","url":null,"abstract":"","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"18 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1991-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73583200","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}
Pub Date : 1991-01-01DOI: 10.1007/978-94-011-2781-3_100
L. Hodgson, S. Apple, R. A. Culp
{"title":"Niobium as an ex-vessel neutron dosimeter for PWRs","authors":"L. Hodgson, S. Apple, R. A. Culp","doi":"10.1007/978-94-011-2781-3_100","DOIUrl":"https://doi.org/10.1007/978-94-011-2781-3_100","url":null,"abstract":"","PeriodicalId":23138,"journal":{"name":"Transactions of the American Nuclear Society","volume":"45 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"1991-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79657245","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}
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