Download or read book Fission product data for thermal reactors part I a data set for EPRI CINDER using ENDF B IV written by T. R. England and published by . This book was released on 1976 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fission Product Data for Thermal Reactors Part 2 Users Manual for EPRI CINDER Code and Data written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The objective of this project has been the production of a data library suitable for calculating the buildup of fission product nuclides during the operation of a thermal power reactor. This has been accomplished by reducing the fission product data from the fourth version of the national reference nuclear data base--ENDF/B into a series of linearized decay chains and calculating the effective yields and cross sections of the relevant nuclides. Two versions of the fission product library have been prepared: an 84 chain master library and a reduced 12 chain library, both of which can be used as input for the computer program CINDER. A users manual for an upgraded version of the burnup program CINDER (renamed EPRI-CINDER) is presented.

Download or read book Energy Research Abstracts written by and published by . This book was released on 1978 with total page 640 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book INIS Atomindex written by and published by . This book was released on 1978 with total page 1212 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fission Product Inventory and Decay Heat Associated with FTR Fuel written by W. L. Bunch and published by . This book was released on 1969 with total page 90 pages. Available in PDF, EPUB and Kindle. Book excerpt: The fission product inventory and the decay heat associated with driver fuel irradiated to goal exposure (45,000 MWd per metric ton) in the Fast Test Reactor is presented, based on calculations using the computer code RIBD with a nuclear data library prepared for the FTR environment. Curie inventories as a function of decay time are given for each of about 350 isotopes or isomeric states generated by the fast-neutron induced fission of either 239Pu or 238U, by down-chain decay, or by subsequent neutron capture. Beta, gamma, and total decay power are given in percent of operating power for decay times from 1 sec to about 10 years. Uncertainty in the decay heat calculations, based on propagation of the uncertainties associated with input nuclear data, is estimated. The uncertainty is calculated to be less than +̲ 10% for the first 10 days, and less than +̲ 20% over a 10-yr decay period.

Download or read book Integral Data Testing of ENDF B Fission product Data and Comparisons of ENDF B with Other Fission Product Data Files written by and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Three experiments (one from Oak Ridge and two from Los Alamos), in which samples of 235U and 238Pu were irradiated with thermal neutrons and either the total, gamma-ray, or gamma- and beta-ray fission product decay-energies were measured as functions of cooling time, were selected for comparisons with calculations made using four different fission product data files. The data files used were (1) the ENDF/B-IV fission product file, (2) the ENDF/B-V fission product file, (3) a file derived by substituting decay energies from JNDC into the ENDF/B-V file, and (4) a file derived by substituting decay-energies and spectra from the UK data file into the ENDF/B-V file. Direct summation calculations and spectral comparisons of the experiments were made using these data files as input, and both types of calculational analyses yielded the same results; namely, all data files are deficient, but the JNDC-ENDF/B-V results for the gamma- and beta-ray total decay-energy agree best with experiments. In addition, spectral comparisons with experiment generally indicate that calculated gamma-ray decay-energies are relatively high for early cooling times and small gamma-ray energies; they are low for early cooling times and large gamma-ray energies. The opposite is somewhat the case for the beta-ray decay energies; that is, the calculations are generally low for small beta-ray energies and high for large energies.

Download or read book Transactions of the American Nuclear Society written by American Nuclear Society and published by . This book was released on 1978 with total page 860 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fission Product Data for Thermal Reactors written by T. R. England and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Government Reports Announcements Index written by and published by . This book was released on 1978-04 with total page 1138 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book ENDF B IV Fission product Files written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The major fission-product parameters [sigma/sub th/, RI, tau12, E- bar/sub $beta$/, E-bar/sub [gamma]/, E-bar/sub $alpha$/, decay and (n, $gamma$) branching, Q, and AWR] abstracted from ENDF/B-IV files for 824 nuclides are summarized. These data are most often requested by users concerned with reactor design, reactor safety, dose, and other sundry studies. The few known file errors are corrected to date. Tabular data are listed by increasing mass number. (auth).

Download or read book ENDF B IV and V Cross Section Libraries for Thermal Power Reactor Analysis written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The NJOY processing system was used to produce thermal reactor cross-section libraries from ENDF/B-IV, and -V evaluations for the fuel cycle codes EPRI-CELL and EPRI-CPM, for the continuous-energy Monte Carlo code MCNP, and for the Los Alamos discrete-ordinates transport codes. This consistent data source allowed the approximate methods (equivalence theory, B1, integral transport, P/sub L/-S/sub N/) to be compared with accurate Monte Carlo results. So far, this has resulted in improved methods for space-and-energy self-shielding in the resonance range (e.g., the NJOY flux calculator, epithermal disadvantage factors for EPRI-CELL, shielded elastic removal), it has shown why the newest ENDF-based libraries initially gave results worse than the old libraries, and it has pointed out problems for future study such as resonance interference effects at high burnup. Finally, the results are compared to various criticality benchmarks to evaluate the performance of ENDF/B-V for thermal reactor analysis and to establish the biases introduced by the approximate methods used in the fuel cycle codes. 3 tables.

Download or read book Evaluation of Fission Product After heat written by B. I. Spinrad and published by . This book was released on 1978 with total page 96 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fission Product Data for Thermal Reactors A data set for EPRI CINDER using ENDF written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fission Product Data for Thermal Reactors Part 1 Cross Sections written by Atomic Energy of Canada Limited and published by . This book was released on 1969 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book ENDF B Fission product Data written by and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: In recognition of the pressing need for nuclear decay data in a variety of reactor-related applications, the scope of the Evaluated Nuclear Data Files (ENDF/B) was expanded to include such information. The initial reason for this expansion was to provide reliable data and a common data base to be used in computer codes developed to carry out summation calculations of the decay-heat source term in reactor cores. The ENDF/B-V fission product file was released in July 1980 and contains data for 877 nuclides. Forty-two of these are found in greater detail on the General Purpose file. Seven hundred and fifty isotopes contain decay data. One hundred and ninety-six contain cross section data for total, elastic, inelastic, and angular distributions in the energy range 10−5 eV to 20 MeV. This special fission product file is contained on 6 magnetic tapes, and is available from the National Nuclear Data Center (NNDC) at BNL. (WHK).

Download or read book Government Reports Annual Index written by and published by . This book was released on 1978 with total page 1304 pages. Available in PDF, EPUB and Kindle. Book excerpt: Sections 1-2. Keyword Index.--Section 3. Personal author index.--Section 4. Corporate author index.-- Section 5. Contract/grant number index, NTIS order/report number index 1-E.--Section 6. NTIS order/report number index F-Z.

Download or read book Status of CINDER and ENDF written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The CINDER codes and their data libraries are described, and their range of calculational capabilities are described using documented applications. The importance of ENDF/B data and the features of the ENDF/B-IV and ENDF/B-V fission-product and actinide data files are emphasized. The actinide decay data of ENDF/B-V, augmented by additional data from available sources, are used to produce average decay energy values and neutron source values from sponteneous fission, (.cap alpha., n) and delayed neutron emission for 144 actinide nuclides that are formed in reactor fuel. The status and characteristics of the CINDER-2 code is described, along with a brief description of more well known code versions; a review of the status of new ENDF/B-V based libraries for all versions is presented.