Prompt gamma activation analysis (PGAA) is a unique, non-destructive nuclear analytical method with multi-element capabilities. It is most effective if intense neutron beams (especially cold beams) of nuclear reactors are used to induce the prompt gamma radiation. Based largely on the authors' pioneering research in cold neutron PGAA, the handbook describes the methodology in self-contained manner and reviews recent applications. The library of prompt gamma ray data and spectra for all natural elements is a unique aid to the practitioner. The level is understandable by a broad audience, which facilitates teaching and training. The Handbook of Prompt Gamma Activation Analysis is a comprehensive handbook written for those practising the method, wanting to implement it at a reactor facility, or just looking for a powerful non-destructive method of element analysis. The book is also useful for nuclear physics, chemistry and engineering scientists, scholars and graduate students interested in neutron-induced gamma ray spectroscopy and nuclear analytical methods.

In this work a prompt gamma neutron activation analysis (PGNAA) facility has been designed, built, and characterized at the Oregon State University TRIGA® reactor. PGNAA is a technique used to determine the presence and quantity of trace elements such as boron, hydrogen and carbon which are more difficult to detect with other neutron analysis methods. In PGNAA, isotopes are subjected to a neutron beam, resulting in the formation of an unstable compound nucleus. The compound nucleus immediately decays, producing a series of gamma-rays, whose energies are distinctive to each element. These gamma-rays are then measured using an HPGe detector to determine the elemental composition of the sample. The measured thermal and epithermal neutron fluxes of the PGNAA facility at Oregon State University are 2.81 x 107 ± 5.13 x 105 cm−2s−1 and 1.70 x 104 ± 3.11 x 102 cm−2s−1 respectively. This gives the facility a cadmium ratio of 106. Measured detection limits for boron, chlorine, and potassium in SRM 1571 orchard leaf standard were, 5.6 x 10−4mg/g, 8.2 x 10−2 mg/g and, 1.0 mg/g respectively. Also, the detection limit for hydrogen in high-density polyethylene is, 6.8 x 10−2mg/g. Detection limits for additional elements are presented in this work.

The nuclear fuel cycle is characterised by the wide range of scientific disciplines and technologies it employs. The development of ever more integrated processes across the many stages of the nuclear fuel cycle therefore confronts plant manufacturers and operators with formidable challenges. Nuclear fuel cycle science and engineering describes both the key features of the complete nuclear fuel cycle and the wealth of recent research in this important field.Part one provides an introduction to the nuclear fuel cycle. Radiological protection, security and public acceptance of nuclear technology are considered, along with the economics of nuclear power. Part two goes on to explore materials mining, enrichment, fuel element design and fabrication for the uranium and thorium nuclear fuel cycle. The impact of nuclear reactor design and operation on fuel element irradiation is the focus of part three, including water and gas-cooled reactors, along with CANDU and Generation IV designs. Finally, part four reviews spent nuclear fuel and radioactive waste management.With its distinguished editor and international team of expert contributors, Nuclear fuel cycle science and engineering provides an important review for all those involved in the design, fabrication, use and disposal of nuclear fuels as well as regulatory bodies and researchers in this field. - Provides a comprehensive and holistic review of the complete nuclear fuel cycle - Reviews the issues presented by the nuclear fuel cycle, including radiological protection and security, public acceptance and economic analysis - Discusses issues at the front-end of the fuel cycle, including uranium and thorium mining, enrichment and fuel design and fabrication