... The process of determining the uncertainty in the neutron fluence from the measured activity of a dosimetry monitor is reviewed and the importance of treating the energy-dependent correlation is illustrated using several representative neutron fields. The process of determining the uncertainty...

...) reactions (or both) and introduces an original post–irradiation analysis for reactor dosimetry based on accelerator mass spectrometry. It also reveals that more precise evaluations of 92 Zr and 94 Zr(n, γ) cross sections are required in order to improve calculation/experiment values. dosimetry...

... In the 1980's the dosimetry community embraced the need for a high fidelity quantification of uncertainty in nuclear data used for dosimetry applications. This led to the adoption of energy-dependent covariance matrices as the accepted manner of quantifying the uncertainty data. The trend...

.... For this purpose, a default spectrum is needed, and one has been calculated with the Monte-Carlo transport code Tripoli 4 using the benchmarked Caliban description. activation dosimetry Fission Reactor Measurement Neutron Spectroscopy spectrum unfolding Reprinted from JAI, Vol. 9, No. 3 doi:10.1520...

.... heavy ion beams fluence measurements 84 Kr 40 Ar dosimetry high-LET dosimetry relative dosimeters chemical dosimeters cellulose triacetate CTA Zofia Peimel-StuglikI and Vladimir A. Skuratov2 Heavy Ion Fiuence Measurements Based on Radiation Effects Generated in CTA Foils Reference: Peimel...

... The JENDL Dosimetry File, which contains 67 dosimetry reactions, has been revised by the Dosimetry Integral Test Working Group of the Japanese Nuclear Data Committee. Thirty-one cross sections and their covariance data were simultaneously evaluated mainly through a generalized least-squares code...

... For the dosimetry of high-energy accelerator neutron sources such as spallation neutron source facilities and the International Fusion Material Irradiation Facility, a dosimetry cross section set up to 50 MeV was produced by means of integral activation experiments. Activation foil samples of Al...

... The real-time dosimetry method using an imaging plate has been studied. A small, remote radiation sensor using commercially available imaging plates has been developed for the purpose. The sensor adopts wavelength shift fibers for signal transmission and side-glow fibers for illumination...

... A new kind of optical dosimetry such as the in-core power monitoring and gamma ray thermometer using radio luminescence and thermal radiation due to gamma ray in optical fibers was demonstrated. During heavy irradiation in the core region of JMTR fission reactor, optical fiber kept good...

... Dosimetry plays a key role in the context of reactor pressure vessel surveillance and lifetime assessment. Uncertainty in the fluence estimate has a direct impact on the integrity assessment and on the operating limits of the reactors, and must be limited. The required precision is discussed...

... The ASTM standards provide guidance and instruction on how to field and interpret reactor dosimetry. They provide a roadmap towards understanding the current “state-of-the-art” in reactor dosimetry, as reflected by the technical community. The consensus basis to the ASTM standards assures...

... The main tasks and problems of VVER reactor pressure vessel (RPV) dosimetry are reviewed taking into account the RPV metal characteristics, the peculiarities of surveillance programs and some features of irradiation embrittlement of VVER-440 and VVER-1000 RPV materials. The problems of dosimetry...

... A new neutron-gamma coupled MATXS-format library, which is designated KASHIL-E6, has been generated for shielding or reactor pressure vessel dosimetry applications. The library was tested against the NESDIP-2 experiment for application to the RPV dosimetry. Dosimetry analyses on the surveillance...

..., and significantly slower dpa rate attenuation through pressure vessel walls relative to the results with their predecessors: the Sailor library and ASTM iron dpa cross sections. ENDF/B-VI neutron transport dosimetry reactor pressure vessel I. Remecl Impact of the ENDF/B-VI Cross Sections on the RPV...

... the SAND-II code. Good agreement was observed between the calculated and measured data. fast neutron irradiation facility research reactors semiconductor irradiation Monte Carlo simulations MCNP dosimetry spectrum unfolding SAND-II Bojan Petrovic,1,3 Attya Abou-Zaid,2 Alireza Haghighat,3...

... to establish relevant thermal balance corrections (i.e., heat losses), the search for low uncertainties during the ramp experiments made it necessary to implement an extensive fuel dosimetry program. This program is based on a specific irradiation run involving nuclear, reactor physics, and radiochemical...

... In order to meet the requirement from the high energy neutron dosimetry application, we have examined potential reactions for the neutron activation detector at spallation neutron fields, which were provided by driving protons with energies of 1.6, 12 and 24 GeV into a mercury target...

..., called here the fluence-dosimetry method, combines the measurement of fluence dosimeters with the calculation of the flux chart inside the irradiation device, and in particular of the flux and the fission density in the fuel. The various factors influencing the accuracy of the latter method...

... Specific physics-dosimetry-metallurgy issues are considered that will impact on current and future revisions of the thirty-four standards that have been identified for the next revision of the ASTM E706 Master Matrix of LWR Surveillance Standards, E706(0). Two major classes of technical issues...

... Vessel (PV) Surveillance Standards. The current version (E706-87) of the Master Matrix identifies 21 ASTM LWR physics-dosimetry-metallurgy standards for Reactor Pressure Vessel (RPV) and Support Structure (SS) surveillance programs, whereas, for the next revision 34 standards are identified...