Dosimetry Issues for an Ultra-high Flux Beam and Multipurpose Research Reactor Design PDF Download
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Author: Publisher: ISBN: Category : Languages : en Pages : 10
Book Description
The Advanced Neutron Source is a new user facility for all fields of neutron research, including neutron beam experiments, materials analysis, materials testing, and isotope production. The complement and layout of the experimental facilities have been determined sufficiently, at a conceptual design level, to make reliable cost and schedule estimates. The source of neutrons will be a heavy water reactor, constructed largely of aluminum, with an available thermal neutron flux 5--10 times higher than existing research reactors. Among the dosimetry issues to be faced are damage prediction and surveillance for component life attainment; measurement of fluence and spectra in regions where both change substantially over a distance of a few centimeters; and characterization and measurement of the radiation field in the research areas around the neutron beam experiments.
Author: Publisher: ISBN: Category : Languages : en Pages : 10
Book Description
The Advanced Neutron Source is a new user facility for all fields of neutron research, including neutron beam experiments, materials analysis, materials testing, and isotope production. The complement and layout of the experimental facilities have been determined sufficiently, at a conceptual design level, to make reliable cost and schedule estimates. The source of neutrons will be a heavy water reactor, constructed largely of aluminum, with an available thermal neutron flux 5--10 times higher than existing research reactors. Among the dosimetry issues to be faced are damage prediction and surveillance for component life attainment; measurement of fluence and spectra in regions where both change substantially over a distance of a few centimeters; and characterization and measurement of the radiation field in the research areas around the neutron beam experiments.
Author: CD. West Publisher: ISBN: Category : Neutron research Languages : en Pages : 10
Book Description
The Advanced Neutron Source is a new user facility for all fields of neutron research, including neutron beam experiments, materials analysis, materials testing, and isotope production. The complement and layout of the experimental facilities have been determined sufficiently, at a conceptual design level, to make reliable cost and schedule estimates. The source of neutrons will be a heavy water reactor, constructed largely of aluminum, with an available thermal neutron flux 5-10 times higher than existing research reactors.
Author: Hamid Ait Abderrahim Publisher: World Scientific ISBN: 9814545317 Category : Languages : en Pages : 959
Book Description
This symposium provided a forum for interchange of state-of-the-art techniques and databases and for standardization of radiation metrology.The proceedings are of value to anyone involved in reactor dosimetry, including researchers, manufacturers, and representatives from industry, utilities and regulatory agencies. The major topics treated are: reactor pressure vessel surveillance and plant life management; reactor dosimetry techniques; benchmarks; nuclear data; damage correlation and exposure parameters; experimental and calculational characterization of irradiation environments; dosimetry for research reactors and irradiation experiments.
Author: Harry Farrar Publisher: ASTM International ISBN: 0803118996 Category : Nuclear reactors Languages : en Pages : 854
Book Description
Proceedings of the 8th ASTM-Euratom Symposium, held in Vail, Colorado, Aug.-Sept. 1993, to provide a forum for experts to discuss their latest results under the broad theme of dosimetry for the correlation of radiation effects. Preceded by a summary of the keynote presentations and followed by summa
Author: Publisher: ISBN: Category : Languages : en Pages : 8
Book Description
RADIATION DOSIMETRY MEASUREMENTS HAVE BEEN PERFORMED OVER A PERIOD OF MANY YEARS AT THE HIGH FLUX BEAM REACTOR (HFBR) AND THE MEDICAL RESEARCH REACTOR (BMRR) AT BROOKHAVEN NATIONAL LABORATORY TO PROVIDE INFORMATION ON THE ENERGY DISTRIBUTION OF THE NEUTRON FLUX, NEUTRON DOSE RATES, GAMMA-RAY FLUXES AND GAMMA-RAY DOSE RATES. THE MCNP PARTICLE TRANSPORT CODE PROVIDED MONTE CARLO RESULTS TO COMPARE WITH VARIOUS DOSIMETRY MEASUREMENTS PERFORMED AT THE EXPERIMENTAL PORTS, AT THE TREATMENT ROOMS AND IN THE THIMBLES AT BOTH HFBR AND BMRR.
Author: RN. Reciniello Publisher: ISBN: Category : Dose rates Languages : en Pages : 8
Book Description
Radiation dosimetry measurements have been performed over a period of many years at the High Flux Beam Reactor (HFBR) and the Medical Research Reactor (BMRR) at Brookhaven National Laboratory to provide information on the energy distribution of the neutron fluxes, neutron dose rates, gamma-ray fluxes and gamma-ray dose rates. The MCNP Particle Transport Code provided Monte Carlo results to compare with various dosimetry measurements performed at the experimental ports, at the treatment rooms and in the thimbles at both the HFBR and BMRR.
Author: Jan Wagemans Publisher: World Scientific ISBN: 9814485489 Category : Science Languages : en Pages : 759
Book Description
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.
Author: A. Edward Profio Publisher: John Wiley & Sons ISBN: Category : Science Languages : en Pages : 568
Book Description
An up-to-date reference and text that discusses the design of shields for radioactive sources, X-ray machines, low energy accelerators, and nuclear reactors. Introduces dosimetry in industry and medicine, examining the prediction and measurement of dose in the body from external and internal sources, and the biological effects of ionization radiation. The unified treatment emphasizes recent practice and includes modern computer methods and results. And, the considerable data presented in tabular and graphical forms provide a ready reference that minimizes the need for supplementary literature.
Author: John G. Williams Publisher: ASTM International ISBN: 0803128843 Category : Nuclear power plants Languages : en Pages : 884
Book Description
Comprising the proceedings of the Tenth International Symposium on Reactor Dosimetry held in Osaka, Japan in September 1999, this volume contains some 100 papers, plus three keynote speeches, arranged in seven sections that cover the technical scope of the symposium. The first two sections consist o