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Download or read book Neutron-Induced Fission Cross Section Measurements for Uranium Isotopes and Other Actinides at LANSCE. written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Fission Cross Section Measurements of Actinides at LANSCE. written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Fission cross sections of a range of actinides have been measured at the Los Alamos Neutron Science Center (LANSCE) in support of nuclear energy applications. By combining measurement at two LANSCE facilities, Lujan Center and the Weapons Neutron Research center (WNR), differential cross sections can be measured from sub-thermal energies up to 200 MeV. Incident neutron energies are determined using the time-of-flight method, and parallel-plate ionization chambers are used to measure fission cross sections relative to the 235U standard. Recent measurements include the {sup 233,238}U, {sup 239,242}Pu and 243Am neutron-induced fission cross sections. In this paper preliminary results for cross section data of 243Am and 233U will be presented.
Download or read book Actinide Neutron-induced Fission Cross Section Measurements at LANSCE. written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Fission cross sections of a range of actinides have been measured at the Los Alamos Neutron Science Center (LANSCE) in support of nuclear energy applications in a wide energy range from sub-thermal energies up to 200 MeV. A parallel-plate ionization chamber are used to measure fission cross sections ratios relative to the 235U standard while incident neutron energies are determined using the time-of-flight method. Recent measurements include the {sup 233,238}U, 239−242Pu and 243Am neutron-induced fission cross sections. Obtained data are presented in comparison with ex isting evaluations and previous data.
Author : Gordon Douglas James
Publisher : Pergamon
ISBN 13 :
Total Pages : 304 pages
Book Rating : 4.:/5 (44 download)
Download or read book Nuclear Fission and Neutron-induced Fission Cross-sections written by Gordon Douglas James and published by Pergamon. This book was released on 1981 with total page 304 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear Fission and Neutron-Induced Fission Cross-Sections is the first volume in a series on Neutron Physics and Nuclear Data in Science and Technology. This volume serves the purpose of providing a thorough description of the many facets of neutron physics in different fields of nuclear applications. This book also attempts to bridge the communication gap between experts involved in the experimental and theoretical studies of nuclear properties and those involved in the technological applications of nuclear data. This publication will be invaluable to those interested in studying nuclear fis.
![Download Measurements of Neutron-induced Fission Cross-section Ratios Involving Isotopes of Uranium and Plutonium. [0. 001 to 30 MeV, Cross Sections]. PDF Online Free](https://books.google.com/books/content/images/frontcover/NdKVAQAACAAJ?fife=w200-h370)
Download or read book Measurements of Neutron-induced Fission Cross-section Ratios Involving Isotopes of Uranium and Plutonium. [0. 001 to 30 MeV, Cross Sections]. written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A procedure, called the threshold cross section method was applied to our experimental data involving four uranium (233U 234U, 236U, and 238U) and five plutonium (239Pu, 24°Pu, 241Pu, 242Pu, and 244Pu) isotopes to determine ratios of fission cross sections relative to 235U. The data were gathered using ionization fission chambers and the time-of-flight technique at the LLL 100-MeV electron linear accelerator: measurements span the neutron energy range of 0.001 to 30 MeV. Experimental uncertainties common to past measurements were either eliminated or significantly reduced in this study by use of the threshold method, thereby making higher accuracies possible. The cross section ratios are absolute in the sense that they do not depend on the work of others. Results from our ratios involving 233U, 235U, 238U, and 239Pu are used to illustrate this method.
Author : Anthony Lloyd Hutcheson
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (286 download)
Download or read book Neutron-Induced Partial Gamma-Ray Cross-Section Measurements on Uranium written by Anthony Lloyd Hutcheson and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Precision measurements of 238U(n, n'g) and 235,238U(n,2ng) partial cross sections have been performed at Triangle Universities Nuclear Laboratory (TUNL) to improve crucial data for the National Nuclear Security Administration's (NNSA) Stockpile Stewardship Program. Accurate neutron-induced reaction cross-section data are required for many practical applications, including nuclear energy and reactor technology, nuclear transmutation, and explosive nuclear devices. Due to the cessation of underground nuclear testing in the early 1990s, understanding of the performance of nuclear devices is increasingly dependent on precise model calculations which are, in turn, themselves reliant on accurate reaction data to serve as benchmarks for model codes. Direct measurement of (n, n') and (n,2n) reaction cross sections for uranium is extremely difficult due to large neutron background from fission and very close nuclear level spacing. Previous direct measurements of the cross sections are incomplete and/or discrepant over the energy range of interest. However, the (n, n'g) and (n,2ng) partial gamma-ray cross-section data obtained in the present work can be combined with model calculations to infer total (n, n') and (n,2n) reaction-channel cross sections. A pulsed and monoenergetic neutron beam was used in combination with high-resolution gamma-ray spectroscopy to measure these partial cross sections for incident neutron energies between 5 and 14 MeV. Gamma-ray yields were measured with high-purity germanium (HPGe) clover and planar detectors. Neutron fluxes were determined from the well-measured 2+ -> 0+ transition in 56Fe to be on the order of 10^4 n/cm^2/s. Detector efficiency and attenuation of gamma rays in the target were simulated using the MCNPX Monte-Carlo radiation transport code. Measured partial cross sections were compared with previous measurements and calculations from GNASH and TALYS Hauser-Feshbach statistical-model codes. Results are generally in good agreement with existing data and provide cross-section data for transitions in energy regions where none previously existed. Total reaction-channel cross sections are inferred from statistical-model calculations and compared with existing direct measurement data.
Download or read book Neutron-induced Fission-cross-section Measurements and Calculations of Selected Transplutonic Isotopes written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The neutron-induced fission cross sections of /sup 242m/Am and 245Cm have been measured over an energy range of 10−4 eV to approx. 20 MeV in a series of experiments at three facilities during the past several years. The combined results of these measurements, in which only sub-milligram quantities of enriched isotopes were used, yield cross sections with uncertainties of approximately 5% below 10 MeV relative to the 235U standard cross section used to normalize the data. We summarize the resonance analysis of the /sup 242m/Am(n, f) cross section in the eV region. Hauser-Feshbach statistical calculations of the detailed fission cross sections of 235U and 245Cm have been carried out over the energy region from 0.1 to 5 MeV and these results are compared with our experimental data.
Author : R. L. Henkel
Publisher :
ISBN 13 :
Total Pages : 28 pages
Book Rating : 4.3/5 (91 download)
Download or read book Summary of Neutron-induced Fission Cross Sections written by R. L. Henkel and published by . This book was released on 1957 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Fission Cross Sections of 23°Th, 232Th, 233U, 234U, 236U, 238U, 237Np, 239Pu and 242Pu Relative 235U at 14. 74 MeV Neutron Energy written by and published by . This book was released on 1986 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The measurement of the fission cross section ratios of nine isotopes relative to 235U at an average neutron energy of 14.74 MeV is described with particular attention to the determination of corrections and to sources of error. The results are compared to ENDF/B-V and to other measurements of the past decade. The ratio of the neutron induced fission cross section for these isotopes to the fission cross section for 235U are: 23°Th - 0.290 +- 1.9%; 232Th - 0.191 +- 1.9%; 233U - 1.132 +- 0.7%; 234U - 0.998 +- 1.0%; 236U - 0.791 +- 1.1%; 238U - 0.587 +- 1.1%; 237Np - 1.060 +- 1.4%; 239Pu - 1.152 +- 1.1%; 242Pu - 0.967 +- 1.0%. 40 refs., 11 tabs., 9 figs.
Author : Athanasios Stamatopoulos
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (137 download)
Download or read book Measurement of the 240Pu(n,f) Cross-section at the CERN N_TOF Facility: First Results from Experimental Area II (EAR-2) written by Athanasios Stamatopoulos and published by . This book was released on 2017 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: The accurate knowledge of the neutron-induced fission cross-sections of actinides and other isotopes involved in the nuclear fuel cycle is essential for the design of advanced nuclear systems, such as Generation-IV nuclear reactors. Such experimental data can also provide the necessary feedback for the adjustment of nuclear model parameters used in the evaluation process, resulting in the further development of nuclear fission models. In the present work, the 240Pu(n,f) cross-section was measured at CERN's n_TOF facility relative to the well-known 235U(n,f) cross section, over a wide range of neutron energies, from meV to almost MeV, using the time-of-flight technique and a set-up based on Micromegas detectors. This measurement was the first experiment to be performed at n_TOF's new experimental area (EAR-2), which offers a significantly higher neutron flux compared to the already existing experimental area (EAR-1). Preliminary results as well as the experimental procedure, including a description of the facility and the data handling and analysis, are presented.
Author : David T. Goldman
Publisher :
ISBN 13 :
Total Pages : 680 pages
Book Rating : 4.3/5 (243 download)
Download or read book Neutron Cross Sections and Technology written by David T. Goldman and published by . This book was released on 1968 with total page 680 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Measurement of the Neutron-induced Fission Cross Section of 241Pu Relative to 235U from 0.001 to 30 MeV. written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The ratio of the neutron-induced fission cross sections of 241Pu relative to that of 235U was measured with fission ionization chambers at the LLL 100-MeV electron linear accelerator. The time-of-flight technique was used to measure the cross-section ratio as a function of neutron energy from 0.001 to 30 MeV. The continuous energy spectrum of the neutron source allowed us to cover the entire energy range in one measurement. Pulse height distributions were also measured as functions of energy over broad energy bands. These data were used to estimate the energy variation in the efficiency to be less than 0.75 percent. The threshold cross-section method normalized the ratio independent of other cross-section measurements to 1.268 +- 0.022 in the interval 1.75 to 4.00 MeV. The ratio was also taken to thermal neutron energy where it was normalized to evaluated thermal fission cross sections and the resulting ratio in the 1.75- to 4.00-MeV interval was 1.242 +- 0.021. Corrected for the impurities in the 241Pu sample, the average of these two values resulted in a $sup 241$Pu:235U fission cross-section ratio of 1.251 +- 0.016 for the normalization interval. Typical energy resolution is 5 percent at 20.0, 1.0, and 0.1 MeV. Most of the data have counting uncertainties smaller than 4 percent, expressed as a standard deviation. Systematic errors are discussed, and current results are compared with previous measurements. Tables of our data are included. (9 tables, 8 figures) (auth).
Author : W. Younes
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (316 download)
Download or read book Tables of Neutron-Induced Fission Cross Section for Various Pu, U, and Th Isotopes, Deduced from Measured Fission Probabilites written by W. Younes and published by . This book was released on 2003 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Cross sections for neutron-induced fission of {sup 231,233}Th, {sup 234,235,236,237,239}U, and {sup 240,241,243}Pu are presented in tabular form for incident neutron energies of 0.1 {le} E{sub n}(MeV) {le} 2.5. The cross sections were obtained by converting measured fission probabilities from (t, pf) reactions on mass-A targets to (n, f) cross sections on mass-A + 1 neutron targets, by using modeling to compensate for the differences in the reaction mechanisms. Data from Britt et al. were used for the {sup 234}U(t, pf) reaction, from Cramer et al. for the {sup 230,232}Th(t, pf), {sup 236,238}U(t, pf), and {sup 240,242}Pu(t, pf) reactions, and from Britt et al. for the {sup 233,235}U(t, pf) and {sup 239}Pu(t, pf) reactions. The fission probabilities P{sub (t, pf)}(E{sub x}), measured as a function of excitation energy E{sub x} of the compound system formed by the (t, p) reaction, are listed in the tables with the corresponding deduced cross sections as a function of incident neutron energy E{sub n}, {sigma}{sub (n, f)}(E{sub n}). The excitation energy and incident neutron energy are related by E{sub x} = E{sub n} + B{sub n}, where B{sub n}, where B{sub n} is the neutron binding energy. Comparison with ENDF/B-VI evaluations of the well-measured {sup 234,235,236}U(n, f) and {sup 240,241}Pu(n, f) cross sections confirms the accuracy of the present results within a 10% standard deviation above E{sub n} = 1 MeV. Below E{sub n} = 1 MeV, localized deviations of at most {+-} 20% are observed.
Download or read book Measurement of Neutron-Induced Nuclear Reaction Cross Sections on Fission-Product Nuclides written by and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : P. B. Hemmig
Publisher :
ISBN 13 :
Total Pages : 572 pages
Book Rating : 4.E/5 ( download)
Download or read book Conference on Neutron Cross Section Technology written by P. B. Hemmig and published by . This book was released on 1966 with total page 572 pages. Available in PDF, EPUB and Kindle. Book excerpt:
![Download Measurements of the Neutron-induced Fission Cross Sections of 24°Pu and 242Pu Relative to 235U. [0. 02 to 30 MeV, Tables]. PDF Online Free](https://books.google.com/books/content/images/frontcover/V4GiwgEACAAJ?fife=w200-h370)
Download or read book Measurements of the Neutron-induced Fission Cross Sections of 24°Pu and 242Pu Relative to 235U. [0. 02 to 30 MeV, Tables]. written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A continuation is given of the fission-cross-section ratio measurements in progress at the Lawrence Livermore Laboratory. Preliminary results are provided for the 24°Pu/235U and 242Pu/235U ratios from 0.02 to 30 MeV and 0.1 to 30 MeV, respectively. Using the threshold-cross-section method, the ratios were normalized to the values 1.368 +- 0.030 and 1.116 +- 0.025, respectively, from 1.75 to 4.00 MeV.
Author : Víctor Alcayne Aicua
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (135 download)
Download or read book Measurement of the 244Cm, 246Cm and 248Cm Neutron-induced Capture Cross Sections at the CERN N_TOF Facility written by Víctor Alcayne Aicua and published by . This book was released on 2022 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Accurate neutron capture cross section data for minor actinides (MAs) are required to estimate the production and transmutation rates of MAs in light water reactors, critical fast reactors like Gen-IV systems, and other innovative reactor systems such as accelerator driven systems (ADS). In particular, 244Cm, 246Cm and 248Cm (244;246;248Cm) play an important role in the transport, storage and transmutation of the nuclear waste of the actual nuclear reactors, due to the contribution of these isotopes to the radiotoxicity, neutron emission, and decay heat in the spent nuclear fuel. Also, capture reactions in these Cm isotopes open the path for the formation of heavier elements such as Bk and Cf. Recent sensitivity studies have shown that the uncertainties in the evaluations of 244;246;248Cm in the resonance region are too big to obtain the desired uncertainties in the characterisation of the spent fuel of conventional nuclear reactors...
