Author: International Atomic Energy Agency. OECD Nuclear Energy AgencyPublisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 576
Book Description
Differential and Integral Nuclear Data Requirements for Shielding Calculations
Author: International Atomic Energy Agency. OECD Nuclear Energy AgencyPublisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 576
Book Description
Differential and Integral Nuclear Data Requiremets for Shielding Calculations
Author: Consistency Among Differential Nuclear Data and Integral Observations
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Successful nuclear design requires adequate prediction of integral design parameters, and this in turn requires an adequate differential nuclear data base. Data bases that apparently permit reduced biases and design margins have been developed by a) least squares adjustment of differential data or b) trial-and-error selection from alternative evaluated data sets. Criticisms and defenses of such procedures are discussed. Useful data adjustment is related to consistency of the combined differential-integral data set and consistency tests related to least squares adjustment procedures are described. An approach to data adjustment is suggested that is contingent on consistency analysis. A FORTRAN code ALVIN has been developed to carry out the indicated data consistency and adjustment calculations, and to compute required sensitivities of integral parameters to nuclear data changes. The sensitivity modules of ALVIN are validated by computing with two distinct methods the cross-section sensitivity profile for neutron penetration through a thick iron shield. The data consistency and adjustment modules DAFT2 (for arbitrary variance-covariance data) and DAFT3 (for differential data base of arbitrary size uncorrelated with integral data) are validated by comparing their results for a set of data for three ZPR criticals. 2 figures, 5 tables, 51 references (auth).
Nuclear Data Requirements for Reactor Shielding Calculations
Author: A.A. AbagyanPublisher:
ISBN:
Category : Calculation methods
Languages : en
Pages : 7
Book Description
NBS Special Publication
Author: Nuclear Cross Sections for Technology
Author: Joseph L. FowlerPublisher:
ISBN:
Category : Cross sections (Nuclear physics)
Languages : en
Pages : 1064
Book Description
Neutron Standards and Applications
Author: Charles D. BowmanPublisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 384
Book Description
Energy Research Abstracts
Author: Nuclear Data Requirements for Fission Reactor Neutronics Calculations
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 11
Book Description
The paper discusses current European nuclear data measurement and evaluation requirements for fission reactor technology applications and problems involved in meeting the requirements. Reference is made to the NEA High Priority Nuclear Data Request List and to the production of the new JEFF-3 library of evaluated nuclear data. There are requirements for both differential (or basic) nuclear data measurements and for different types of integral measurement critical facility measurements and isotopic sample irradiation measurements. Cross-section adjustment procedures are being used to take into account the simpler types of integral measurement, and to define accuracy needs for evaluated nuclear data.
Physics of Nuclear Reactors
Author: P. MohanakrishnanPublisher: Elsevier
ISBN: 012822441X
Category : Science
Languages : en
Pages : 786
Book Description
Physics of Nuclear Reactors presents a comprehensive analysis of nuclear reactor physics. Editors P. Mohanakrishnan, Om Pal Singh, and Kannan Umasankari and a team of expert contributors combine their knowledge to guide the reader through a toolkit of methods for solving transport equations, understanding the physics of reactor design principles, and developing reactor safety strategies. The inclusion of experimental and operational reactor physics makes this a unique reference for those working and researching nuclear power and the fuel cycle in existing power generation sites and experimental facilities. The book also includes radiation physics, shielding techniques and an analysis of shield design, neutron monitoring and core operations. Those involved in the development and operation of nuclear reactors and the fuel cycle will gain a thorough understanding of all elements of nuclear reactor physics, thus enabling them to apply the analysis and solution methods provided to their own work and research. This book looks to future reactors in development and analyzes their status and challenges before providing possible worked-through solutions. Cover image: Kaiga Atomic Power Station Units 1 - 4, Karnataka, India. In 2018, Unit 1 of the Kaiga Station surpassed the world record of continuous operation, at 962 days. Image courtesy of DAE, India. Includes methods for solving neutron transport problems, nuclear cross-section data and solutions of transport theory Dedicates a chapter to reactor safety that covers mitigation, probabilistic safety assessment and uncertainty analysis Covers experimental and operational physics with details on noise analysis and failed fuel detection