Continuous Monitoring of Fission Gas Release During Irradiation of Nuclear Fuel Specimens PDF Download
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Category :
Languages : en
Pages : 15
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A program is in progress at Battelle-Columbus which is aimed at developing a basic understanding of the mechanisms and processes which contribute to the phenomenology of swelling and fission gas release in nuclear fuel materials during irradiation. As part of this program, neutron radiography has been used to obtain data on the dimensional changes of fuel specimens periodically during irradiation. This data is used to develop plots of fuel swelling as a function of burnup for the specimens under irradiation. These data show a decided nonlinearity of swelling with accumulated burnup for many specimens, and it has been postulated that the shape of the curves is due, at least in part, to the gas release characteristics of the specimens. Accordingly, it was considered advantageous to develop a system to continuously monitor fission gas release from the fuel during irradiation. The system developed consists of a null-balance pressure transducer attached directly to a clad fuel specimen in the capsule. Fission gases escaping from the fuel collect within the cladding and exert pressure on a diaphragm in the transducer. A balancing pressure is introduced on the other side of the diaphragm and the null-balance position of the diaphragm is detected by an electrical contact which is part of a detection circuit. Instrumentation is provided to monitor the balance pressure, and the fission gas temperature and pressure is correlated with the known fission gas generation rate to calculate the fractional release from the fuel. In addition to monitoring fission gas release, the system also provides information on cladding integrity. Cladding failure is detected as a large reduction in pressure while operating at essentially constant temperature. This system has been used successfully in two irradiation experiments at fuel and cladding temperatures in excess of 1700 C. The data it provides on fission gas release has been used in conjunction with swelling data from neutron radiography to provide considerable insight into the phenomenology of the behavior of nuclear fuels during irradiation.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 15
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Book Description
A program is in progress at Battelle-Columbus which is aimed at developing a basic understanding of the mechanisms and processes which contribute to the phenomenology of swelling and fission gas release in nuclear fuel materials during irradiation. As part of this program, neutron radiography has been used to obtain data on the dimensional changes of fuel specimens periodically during irradiation. This data is used to develop plots of fuel swelling as a function of burnup for the specimens under irradiation. These data show a decided nonlinearity of swelling with accumulated burnup for many specimens, and it has been postulated that the shape of the curves is due, at least in part, to the gas release characteristics of the specimens. Accordingly, it was considered advantageous to develop a system to continuously monitor fission gas release from the fuel during irradiation. The system developed consists of a null-balance pressure transducer attached directly to a clad fuel specimen in the capsule. Fission gases escaping from the fuel collect within the cladding and exert pressure on a diaphragm in the transducer. A balancing pressure is introduced on the other side of the diaphragm and the null-balance position of the diaphragm is detected by an electrical contact which is part of a detection circuit. Instrumentation is provided to monitor the balance pressure, and the fission gas temperature and pressure is correlated with the known fission gas generation rate to calculate the fractional release from the fuel. In addition to monitoring fission gas release, the system also provides information on cladding integrity. Cladding failure is detected as a large reduction in pressure while operating at essentially constant temperature. This system has been used successfully in two irradiation experiments at fuel and cladding temperatures in excess of 1700 C. The data it provides on fission gas release has been used in conjunction with swelling data from neutron radiography to provide considerable insight into the phenomenology of the behavior of nuclear fuels during irradiation.
Author: J. M. Markowitz
Publisher:
ISBN:
Category : Fission gases
Languages : en
Pages : 62
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Author: R. M. Carroll
Publisher:
ISBN:
Category : Nuclear fission
Languages : en
Pages : 38
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Author: Russell H. Barnes
Publisher:
ISBN:
Category : Fission gases
Languages : en
Pages : 20
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Author:
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Category :
Languages : en
Pages :
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The AGR-1 experiment is a fueled multiple-capsule irradiation experiment that was irradiated in the Advanced Test Reactor (ATR) from December 26, 2006 until November 6, 2009 in support of the Very High Temperature Reactor (VHTR) Technology Development Office (TDO) Fuel Development and Qualification program. An important measure of the fuel performance is the quantification of the fission product releases over the duration of the experiment. To provide this data for the inert fission gasses(Kr and Xe), a fission product monitoring system (FPMS) was developed and implemented to monitor the individual capsule effluents for the radioactive species. The FPMS continuously measured the concentrations of various krypton and xenon isotopes in the sweep gas from each AGR-1 capsule to provide an indicator of fuel irradiation performance. Spectrometer systems quantified the concentrations of Kr-85m, Kr-87, Kr-88, Kr-89, Kr-90, Xe-131m, Xe-133, Xe 135, Xe 135m, Xe-137, Xe-138, and Xe-139 accumulated over repeated eight hour counting intervals.-. To determine initial fuel quality and fuel performance, release activity for each isotope of interest was derived from FPMS measurements and paired with a calculation of the corresponding isotopic production or birthrate. The release activities and birthrates were combined to determine Release-to-Birth ratios for the selected nuclides. R/B values provide indicators of initial fuel quality and fuel performance during irradiation. This paper presents a brief summary of the FPMS, the release to birth ratio data for the AGR-1 experiment and preliminary comparisons of AGR-1 experimental fuels data to fission gas release models.
Author: Michael B. Weinstein
Publisher:
ISBN:
Category : Fission gases
Languages : en
Pages : 68
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A sweep gas facility has been used to measure the release rates of radioactive fission gases from small UN specimens irradiated to 8-percent burnup at high fission-rate densities. The measured release rates have been correlated with an equation whose terms correspond to direct recoil release, fission-enhanced diffusion, and atomic diffusion (a function of temperature). Release rates were found to increase linearly with burnups between 1.5 and 8 percent. Pore migration was observed after operation at 1550 K to over 6 percent burnup.
Author: Michael B. Weinstein
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ISBN:
Category :
Languages : en
Pages : 22
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Author:
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 804
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Author: National Research Council
Publisher: National Academies Press
ISBN: 0309255716
Category : Medical
Languages : en
Pages : 424
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Book Description
In the late 1980s, the National Cancer Institute initiated an investigation of cancer risks in populations near 52 commercial nuclear power plants and 10 Department of Energy nuclear facilities (including research and nuclear weapons production facilities and one reprocessing plant) in the United States. The results of the NCI investigation were used a primary resource for communicating with the public about the cancer risks near the nuclear facilities. However, this study is now over 20 years old. The U.S. Nuclear Regulatory Commission requested that the National Academy of Sciences provide an updated assessment of cancer risks in populations near USNRC-licensed nuclear facilities that utilize or process uranium for the production of electricity. Analysis of Cancer Risks in Populations near Nuclear Facilities: Phase 1 focuses on identifying scientifically sound approaches for carrying out an assessment of cancer risks associated with living near a nuclear facility, judgments about the strengths and weaknesses of various statistical power, ability to assess potential confounding factors, possible biases, and required effort. The results from this Phase 1 study will be used to inform the design of cancer risk assessment, which will be carried out in Phase 2. This report is beneficial for the general public, communities near nuclear facilities, stakeholders, healthcare providers, policy makers, state and local officials, community leaders, and the media.
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 554
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