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Database of Prompt Gamma Rays from Slow Neutron Capture of Elemental Analysis
IAEA, Vienna, 2007, -251p. (анг. язык)

The increasing importance of prompt gamma ray activation analysis (PGAA) in a broad range of applications is evident, and has been emphasized at many meetings related to this topic. Furthermore, an Advisory Group Meeting (AGM) for the Coordination of the Inteational Network of Nuclear Structure and Decay Data Evaluators concluded that there is a need for a complete library of gamma ray and cross-section data from cold and thermal neutron capture (the AGM was held in Budapest, 14–18 October 1996); this AGM also recommended the organization of an IAEA Coordinated Research Project (CRP) on this subject. The nuclear data programmes of the IAEA arose as a consequence of the advisory reviews of the Inteational Nuclear Data Committee (INDC). At a biennial meeting in 1997, the INDC strongly recommended that the IAEA support new measurements and update the database on the analysis of prompt gamma ray activation induced by neutrons.
As a consequence of the various recommendations, a CRP, entitled Development of a Database for Prompt Gamma Ray Neutron Activation Analysis (PGAA), was initiated in 1999. Prior to this project, several consultants had defined the scope, objectives and tasks of this CRP, as approved subsequently by the IAEA. Each CRP participant assumed responsibility for the execution of specific tasks. The results of their work and of other research were discussed and approved by the participants in Research Coordination Meetings (RCMs) held in 2000, 2001 and 2003.
Prompt gamma ray activation analysis is a non-destructive radioanalytical method capable of rapid or simultaneous in situ multielement analyses across the entire periodic table, from hydrogen to uranium. However, inaccurate and incomplete data have been a significant hindrance in the qualitative and quantitative analyses of complicated neutron capture gamma spectra by means of PGAA. Therefore, the main goal of the CRP was to improve the quality and quantity of the required data in order to make possible the reliable application of PGAA in fields such as materials science, chemistry, geology, mining, archaeology, the environment, food analysis and medicine. This aim was achieved due to the dedicated work and effort of the participants. The CD-ROM included with this publication contains the database, retrieval system, three RCM reports, and other important electronic documents related to the project (see also Chapter 8).

CONTENTS
INTRODUCTION
NOMENCLATURE, WESTCOTT gW FACTORS AND NEUTRON SPECTRAL SHAPE DEPENDENT FORMALISM
Introduction
Definitions and nomenclature
Generalized formalism
Concluding remarks
CHARACTERISTICS OF PGAA FACILITIES
The SNU-KAERI PGAA facility and diffracted polychromatic neutron beams
Characterization of prompt gamma neutron activation analysis at the Dalat research reactor
Prompt gamma activation analysis at NIST
Neutron capture gamma ray facilities at the Budapest Research Reactor
Prompt gamma ray neutron activation analysis at the Bhabha Atomic Research Centre
Summary of experimental facilities
Experiments
BENCHMARKS AND REFERENCE MATERIALS
Introduction
Characterization of neutron beams
Analysis of unknown samples
Cross-section measurements
THERMAL NEUTRON CAPTURE CROSS-SECTIONS AND NEUTRON SEPARATION ENERGIES
Introduction
Thermal cross-section evaluation methodology
Adopted thermal neutron cross-sections
Experimental thermal neutron cross-sections
Neutron separation energies
DATA SOURCES AND EVALUATION METHODOLOGY
Prompt gamma ray source databases
Evaluation databases
Adopted gamma ray energies
Adopted gamma ray cross-sections
Radioactive decay data
ADOPTED DATABASE AND USER TABLES
Introduction
Presentation of numerical uncertainty
Isotopic data
Radioactive decay data
The k0 formulation
PGAA data tables
CD-ROM FOR THE IAEA-PGAA DATABASE
Introduction
The IAEA-PGAA database viewer
The PGAA data files
The evaluated gamma ray activation file
PGAA database evaluation
The Isotope Explorer 2.2 ENSDF viewer
APPENDIX I. GAMMA RAY CROSS-SECTION DATA MEASURED WITH THE THERMAL NEUTRON BEAM OF THE BUDAPEST REACTOR
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