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A data development project (International Reactor Dosimetry File or IRDF 2002) was initiated in 2001 to create a current, tested and standardised reactor dosimetry cross-section database with associated uncertainty data for use in the service lifetime assessment of nuclear power reactors. This publication describes the selection procedure and contents of the database and includes a CD-ROM containing the full contents of the IRDF-2002 data library. This set of recommended high-quality data is also appropriate for use in other neutron metrology applications, such as boron neutron capture therapy, therapeutic use of radioisotopes, nuclear physics measurements and reactor safety studies.
This book presents the state of the art in reactor dosimetry as applied to nuclear power plants and to high performance research reactors, accelerator-driven systems and spallation sources. The reader will also find the latest advances in computer code development for radiation transport and shielding. In addition, the book focuses on radiation measurement techniques.
This book gives the state of the art in the field of reactor dosimetry as applied in nuclear power plants and research reactors. Surveillance programs are presented for nuclear power plants in Europe, including Russia and Ukraine, USA, Argentina and Korea. New cross-section measurements from most of the European, American and Japanese research reactors are reported. The latest developments in computer code development for radiation transport and shielding calculations, and radiation measurement techniques are also highlighted.
This is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering. Addressing nuclear engineers and scientists at all levels, this book provides a condensed reference on nuclear engineering since 1958.
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"The latest edition of this popular ASTM series provides an extensive overview of the latest advances in reactor dosimetry. As operating nuclear power reactors have aged and continue to operate on extended operating licenses, new pressure vessel surveillance techniques have been required. Eastern European pressurized water reactors, especially those of the VVER-440 type, continue to have greater concerns about steel embrittlement, because of higher neutron radiation exposures than most Western European and US reactors. Accordingly, broader dosimetry studies are being made on the VVER reactors through retrospective dosimetry, ex-vessel dosimetry, and careful re-analysis of previously reported data."--Publisher's website.