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Temperature and Void Reactivity Coefficient Calculations for the High Flux Isotope Reactor Safety Analysis Report

Temperature and Void Reactivity Coefficient Calculations for the High Flux Isotope Reactor Safety Analysis Report PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 39

Book Description


Temperature and Void Reactivity Coefficient Calculations for the High Flux Isotope Reactor Safety Analysis Report

Temperature and Void Reactivity Coefficient Calculations for the High Flux Isotope Reactor Safety Analysis Report PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 39

Book Description


Reactor Physics Input to the Safety Analysis Report for the High Flux Isotope Reactor

Reactor Physics Input to the Safety Analysis Report for the High Flux Isotope Reactor PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 124

Book Description
HFIR specific, few group neutron and coupled neutron-gamma libraries have been prepared. These are based on data from ENDF/B-V and beginning-of-life (BOL) conditions. The neutron library includes actinide data for curium target rods. Six critical experiments, collectively designated HFIR critical experiment 4, were analyzed. Calculated k-effective was 2% high at BOL-typical conditions but was 1.0 at end-of-life-typical conditions. The local power density distributions were calculated for each of the critical experiments. The axially averaged values at a given radius were frequently within experimental error. However at individual points, the calculated local power densities were significantly different from the experimentally derived values (several times greater than experimental uncertainty). A reassessment of the foil activation data with transport theory techniques seems desirable. Using the results of the critical experiments study, a model of current HFIR configuration was prepared. As with the critical experiments, BOL k-effective was high (3%). However, end-of-life k-effective was high (2%). The end-of-life concentrations of fission products were compared to those generated using the ORIGEN code. Agreement was generally good through differences in the inventories of some important nuclides, Xe and I, need to be understood. End-of-cycle curium target isotopics based on measured, discharged target rods were compared to calculated values and agreement was good. Axial flux plots at various irradiation positions were generated. Time-dependent power distributions based on two-dimensional calculations were provided.

The High Flux Isotope Reactor Accident Analysis

The High Flux Isotope Reactor Accident Analysis PDF Author: F. T. Binford
Publisher:
ISBN:
Category : Nuclear reactor accidents
Languages : en
Pages : 294

Book Description


Heat Transfer Calculations for the High Flux Isotope Reactor (HFIR). Technical Specifications

Heat Transfer Calculations for the High Flux Isotope Reactor (HFIR). Technical Specifications PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
Heat transfer analyses, in support of the preparation of the HFIR technical specifications, were made to establish the bases for the safety limits and limiting safety system settings applicable to the HFIR. The results of these analyses, along with the detailed bases, are presented.

INIS Atomindex

INIS Atomindex PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 682

Book Description


Nuclear Data for Science and Technology

Nuclear Data for Science and Technology PDF Author: Syed M. Qaim
Publisher: Springer Science & Business Media
ISBN: 3642581137
Category : Science
Languages : en
Pages : 1041

Book Description
This book describes the Proceedings of the International Conference on Nuclear Data for Science and Technology held at Jillich in May 1991. The conference was in a series of application oriented nuclear data conferences organized in the past under the auspices of the Nuclear Energy Agency-Nuclear Data Committee (NEANDC) and with the support of the Nuclear Energy Agency-Committee on Reactor Physics (NEACRP). It was the fIrst international conference on nuclear data held in Germany, with the scientific responsibility entrusted to the Institute of Nuclear Chemistry of the Research Centre Jillich. The scientific programme was established by the International Programme Committee in consultation with the International Advisers, and the NEA and IAEA cooperated in the organization. A total of 328 persons from 37 countries and fIve international organizations participated. The scope of these Proceedings extends to a wide range of interdisciplinary topics dealing with measu rement, calculation, evaluation and application of nuclear data, with a major emphasis on numerical data. Both energy and non-energy related applications are considered and due attention is given to some fundamental aspects relevant to the understanding of nuclear data.

Calculation of Doppler Coefficient and Other Safety Parameters for a Large Fast Oxide Reactor

Calculation of Doppler Coefficient and Other Safety Parameters for a Large Fast Oxide Reactor PDF Author: P. Greebler
Publisher:
ISBN:
Category : Fast reactors
Languages : en
Pages : 48

Book Description


Nuclear Safety

Nuclear Safety PDF Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 612

Book Description


Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 612

Book Description


Safety Margins of Operating Rectors

Safety Margins of Operating Rectors PDF Author: M. Antila
Publisher: International Atomic Energy Agency
ISBN: 9789201181022
Category : Business & Economics
Languages : en
Pages : 145

Book Description
This TECDOC deals with a basic concept of safety margins and their role in assuring safety of nuclear Installations. The document describes capabilities of thermal hydraulic computer codes used to determine safety margins, evaluation of uncertainties, methods for safety margin evaluation and utilization of safety margins in operation and modifications of nuclear power plants.