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1.
Rev Sci Instrum ; 85(11): 11D818, 2014 Nov.
Article in English | MEDLINE | ID: mdl-25430231

ABSTRACT

An overview of the diagnostics which are essential for the first operational phase of Wendelstein 7-X and the set of diagnostics expected to be ready for operation at this time are presented. The ongoing investigations of how to cope with high levels of stray Electron Cyclotron Resonance Heating (ECRH) radiation in the ultraviolet (UV)/visible/infrared (IR) optical diagnostics are described.

2.
Radiat Prot Dosimetry ; 161(1-4): 352-6, 2014 Oct.
Article in English | MEDLINE | ID: mdl-24403346

ABSTRACT

A new thermal neutron calibration facility based on a moderator assembly has been set up at PTB. It consists of 16 (241)Am-Be radionuclide sources mounted in a graphite block, 1.5 m wide, 1.5 m high and 1.8 m deep. The sources are distributed to eight different positions, at a mean distance of ∼1.25 m from the front face of the moderator. The neutron field at the reference position, 30 cm in front of the moderator device and 75 cm above the floor, has been characterised using calculations, Bonner sphere measurements and gold foil activation. First results are shown. The field is highly thermalised: 99 % in terms of fluence. It is quite homogenous within a 20 cm×20 cm area, but the absolute value of the thermal neutron fluence rate is small and yields an ambient dose equivalent rate of 3 µSv h(-1).


Subject(s)
Calibration , Neutrons , Radiation Protection/instrumentation , Radiometry/instrumentation , Radiometry/methods , Americium , Beryllium , Cadmium , Equipment Design , Facility Design and Construction , Germanium , Germany , Graphite , Incidence , Monte Carlo Method , Nuclear Reactors , Phantoms, Imaging , Polyethylene , Radiation Protection/methods , Reproducibility of Results , Temperature
3.
Radiat Prot Dosimetry ; 161(1-4): 326-30, 2014 Oct.
Article in English | MEDLINE | ID: mdl-24162373

ABSTRACT

The stellarator Wendelstein 7-X (W7-X), presently under construction at the Max-Planck-Institute for Plasma Physics in Greifswald, will be equipped with a set of neutron monitors to measure the total annual neutron emission for official documentation and to provide information for plasma diagnostics purposes. The authors performed MCNP calculations to design and optimise the moderator geometry of the monitors to exhibit a nearly energy-independent response as well as particular angular responses for one central and two peripheral monitors. The monitors were designed with up to five neutron detector tubes with different sensitivity to thermal neutrons to cover the expected neutron emission rates of W7-X from 10(11) s(-1) to 10(16) s(-1). A prerequisite for the determination of the neutron emission produced by a D-D plasma is an in-situ calibration of the neutron monitors. Such a procedure requires a MCNP simulation of the entire geometry of the W7-X stellarator. In a first benchmark experiment during the assembly phase of W7-X, the validity of the W7-X MCNP model was tested.


Subject(s)
Neutrons , Radiation Protection/methods , Radiometry/instrumentation , Radiometry/methods , Benchmarking , Calibration , Computer Simulation , Equipment Design , Germany , Monte Carlo Method , Radiation Dosage , Scattering, Radiation
4.
Radiat Meas ; 45(10): 1233-1237, 2010 Dec.
Article in English | MEDLINE | ID: mdl-22888283

ABSTRACT

In a recent work, we constructed modular multisphere system which expands upon the design of an existing, commercially available Bonner sphere system by adding concentric shells of copper, tungsten, or lead. Our modular multisphere system is referred to as the Bonner Sphere Extension (BSE). The BSE was tested in a high energy neutron beam (thermal to 800 MeV) at Los Alamos Neutron Science Center and provided improvement in the measurement of the neutron spectrum in the energy regions above 20 MeV when compared to the standard BSS (Burgett, 2008 and Howell et al., 2009).However, when the initial test of the system was carried-out at LANSCE, the BSE had not yet been calibrated. Therefore the objective of the present study was to perform calibration measurements. These calibration measurements were carried out using monoenergetic neutron ISO 8529-1 reference beams at the Physikalisch-Technische Bundesanstalt (PTB), Braunschweig, Germany. The following monoenergetic reference beams were used for these experiments: 14.8 MeV, 1.2 MeV, 565 keV, and 144 keV. Response functions for the BSE were calculated using the Monte Carlo N-Particle Code, eXtended (MCNPX). The percent difference between the measured and calculated responses was calculated for each sphere and energy. The difference between measured and calculated responses for individual spheres ranged between 7.9 % and 16.7 % and the arithmetic mean for all spheres was (10.9 ± 1.8) %. These sphere specific correction factors will be applied for all future measurements carried-out with the BSE.

5.
Radiat Prot Dosimetry ; 126(1-4): 491-6, 2007.
Article in English | MEDLINE | ID: mdl-17496292

ABSTRACT

The European Commission is funding within its Sixth Framework Programme a three-year project (2005-2007) called CONRAD, COordinated Network for RAdiation Dosimetry. The organisational framework for this project is provided by the European Radiation Dosimetry Group EURADOS. One task within the CONRAD project, Work Package 6 (WP6), was to provide a report outlining research needs and research activities within Europe to develop new and improved methods and techniques for the characterisation of complex radiation fields at workplaces around high-energy accelerators, but also at the next generation of thermonuclear fusion facilities. The paper provides an overview of the report, which will be available as CERN Yellow Report.


Subject(s)
Neutrons , Nuclear Fusion , Nuclear Reactors , Occupational Exposure/analysis , Particle Accelerators/instrumentation , Radiation Protection/instrumentation , Radiometry/instrumentation , Equipment Design , Equipment Failure Analysis , Europe , Radiation Dosage , Radiation Protection/methods , Radiometry/methods , Reproducibility of Results , Sensitivity and Specificity
6.
Radiat Prot Dosimetry ; 126(1-4): 482-6, 2007.
Article in English | MEDLINE | ID: mdl-17496297

ABSTRACT

In neutron reference radiation fields, the conventional true value of the personal dose equivalent, H(p)(10), is derived from the spectral neutron fluence and recommended conversion coefficients. This procedure requires the phantom on which the personal dosemeter is mounted to be irradiated with a broad and parallel beam. In many practical situations, the change of the neutron fluence and/or the energy distribution over the surface of the phantom may not be neglected. For a selection of typical irradiation conditions in neutron reference radiation fields, the influence of this effect has been analysed using numerical methods. A further problem, which is of relevance for the calibration of dosemeters measuring both the neutron and the photon component of mixed fields, is the 'double counting' of the dose equivalent due to neutron-induced photons. The relevance of this conceptual problem for calibrations in mixed-field dosimetry was analysed.


Subject(s)
Artifacts , Neutrons , Photons , Radiation Protection/instrumentation , Radiation Protection/standards , Radiometry/instrumentation , Radiometry/standards , Calibration , Equipment Design , Equipment Failure Analysis , Germany , Radiation Dosage , Reproducibility of Results , Sensitivity and Specificity
7.
Radiat Prot Dosimetry ; 116(1-4 Pt 2): 640-6, 2005.
Article in English | MEDLINE | ID: mdl-16604717

ABSTRACT

Measured neutron energy fluences from high-energy heavy ion reactions through targets several centimeters to several hundred centimeters thick were compared with calculations made using the recently developed general-purpose particle and heavy ion transport code system (PHITS). It was confirmed that the PHITS represented neutron production by heavy ion reactions and neutron transport in thick shielding with good overall accuracy.


Subject(s)
Heavy Ions , Models, Statistical , Neutrons , Nuclear Fission , Radiometry/methods , Computer Simulation , Linear Energy Transfer , Radiation Dosage , Scattering, Radiation
8.
Radiat Prot Dosimetry ; 110(1-4): 129-34, 2004.
Article in English | MEDLINE | ID: mdl-15353635

ABSTRACT

The neutron energy spectrum of the JRC 241Am-Li(alpha,n) radionuclide source has been measured at the PTB in Germany using various spectrometry systems, such as Bonner spheres, proton recoil counters and NE213 liquid scintillators. The source photon spectrum has been measured and the neutron contamination due to traces of beryllium through the 9Be(alpha,n)12C reaction has been determined. The effects associated with source encapsulation and the materials it contains have been investigated previously, using Monte Carlo simulations, the various structures seen in the spectra have been explained and the anisotropy of fluence distributions in 4pi have been calculated and compared to measurements. These extensive high resolution spectrometry measurements have been coupled to Monte Carlo calculations to provide a realistic spectrum and new spectrum-averaged fluence-to-dose equivalent conversion coefficients for the actual 241Am-Li source.


Subject(s)
Americium/analysis , Lithium/analysis , Neutrons , Radiation Protection/methods , Radiation Protection/standards , Radiometry/methods , Radiometry/standards , Body Burden , Calibration/standards , Computer Simulation , Computer-Aided Design , Equipment Failure Analysis/instrumentation , Equipment Failure Analysis/methods , Equipment Failure Analysis/standards , Germany , Internationality , Models, Statistical , Monte Carlo Method , Nuclear Reactors , Occupational Exposure/analysis , Photons , Radiation Dosage , Radiation Protection/instrumentation , Radioisotopes/analysis , Radiometry/instrumentation , Reference Standards , Relative Biological Effectiveness , Reproducibility of Results , Scattering, Radiation , Sensitivity and Specificity
9.
Radiat Prot Dosimetry ; 110(1-4): 523-7, 2004.
Article in English | MEDLINE | ID: mdl-15353702

ABSTRACT

The new CANEL/T400 facility has been set-up at the Institute for Radiological Protection and Nuclear Safety (IRSN) to produce a realistic neutron field. The accurate characterisation of this neutron field is mandatory since this facility will be used as a reference neutron source. For this reason an international measuring campaign, involving four laboratories with extensive expertise in neutron metrology and spectrometry, was organised through a concerted EUROMET project. Measurements were performed with Bonner sphere (BS) systems to determine the energy distribution of the emitted neutrons over the whole energy range (from thermal energy up to a few MeV). Additional measurements were performed with proton recoil detectors to provide detailed information in the energy region above 90 keV. The results obtained by the four laboratories are in agreement with each other and are compared with a calculation performed with the MCNP4C Monte-Carlo code. As a conclusion of this exercise, a reliable characterisation of the CANEL/T400 neutron field is obtained.


Subject(s)
Calibration/standards , Equipment Failure Analysis/standards , Neutrons , Radiation Protection/instrumentation , Radiation Protection/standards , Radiometry/instrumentation , Radiometry/standards , Algorithms , Body Burden , Equipment Design , Equipment Failure Analysis/methods , Europe , Feasibility Studies , Humans , Radiation Dosage , Radiation Protection/methods , Radiometry/methods , Reference Standards , Relative Biological Effectiveness , Reproducibility of Results , Risk Assessment/methods , Risk Assessment/standards , Risk Factors , Sensitivity and Specificity
10.
Radiat Prot Dosimetry ; 110(1-4): 533-7, 2004.
Article in English | MEDLINE | ID: mdl-15353704

ABSTRACT

A directional spectrometer that uses a superheated emulsion of dichlorotetrafluoroethane at the centre of a 30 cm diameter moderating-sphere of nylon-6. The system has a telescope-design wherein the detector views a narrow solid angle of about 1/6 steradians. The hydrogenous sphere effectively attenuates laterally incident neutrons, thus providing a strong angular dependence of the response. The central detector is sequentially operated at seven temperatures between 25 and 55 degrees C in order to generate a matrix of nested response functions suitable for few-channel spectrometry. The response matrix of the system has been determined by calibrations with monoenergetic neutrons and by Monte Carlo neutron transport calculations. The double-differential unfolding method developed for this system applies the principle of maximum entropy and allows for the rigorous use of all a priori information. The spectrometer is intended for use in the mixed neutron/photon fields encountered in the nuclear power industry, being suitable for spatially distributed radiation sources with maximum neutron energies up to 10 MeV.


Subject(s)
Equipment Failure Analysis/methods , Neutrons , Radiation Protection/instrumentation , Radiometry/instrumentation , Risk Assessment/methods , Spectrum Analysis/instrumentation , Anisotropy , Body Burden , Equipment Design , Feasibility Studies , Humans , Linear Energy Transfer , Radiation Dosage , Radiation Protection/methods , Radiometry/methods , Relative Biological Effectiveness , Reproducibility of Results , Risk Factors , Sensitivity and Specificity , Spectrum Analysis/methods
11.
Adv Space Res ; 14(10): 815-24, 1994 Oct.
Article in English | MEDLINE | ID: mdl-11540030

ABSTRACT

LET spectra have been measured for lunar missions and for several near Earth orbits ranging from 28 degrees to 83 degrees inclination. In some of the experiments the flux of GCR was determined separately from contributions caused by interactions in the detector material. Results of these experiments are compared to model calculations. The general agreement justifies the use of the model to calculate GCR fluxes. The magnitude of variations caused by solar modulation, geomagnetic shielding, and shielding by matter determined from calculated LET spectra is generally in agreement with experimental data. However, more detailed investigations show that there are some weak points in modeling solar modulation and shielding by material. These points are discussed in more detail.


Subject(s)
Cosmic Radiation , Linear Energy Transfer , Models, Theoretical , Radiation Protection , Radiometry , Space Flight/instrumentation , Magnetics , Solar Activity , Spacecraft/instrumentation , Spectrum Analysis
12.
Adv Space Res ; 14(10): 969-77, 1994 Oct.
Article in English | MEDLINE | ID: mdl-11540042

ABSTRACT

Radiation effects of cosmic ray nuclei are generally described as a function of the particle LET. For a large number of space missions LET spectra have been measured and models have been developed to calculate these spectra that include the effects of geomagnetic shielding and shielding provided by material. In this paper we compare measured and calculated LET spectra. For low earth orbits events with high local energy deposition, i.e., short range secondaries, contribute significantly to the measured spectra. These events are produced by nuclear interactions, mainly induced by protons from the south atlantic anomaly. The technique to include these contributions in the models depends on the size of radiation sensitive volumes. For sizes comparable to or larger than the range of target secondaries it is essential to separate contributions by target interactions from those of cosmic rays. This separation is possible in experiments which use stacks of plastic nuclear track detectors. The yield of short range events generated by protons and measured in the detector can be calibrated from accelerator experimental data. We present first results for CR-39 detectors.


Subject(s)
Cosmic Radiation , Linear Energy Transfer , Models, Theoretical , Protons , Radiation Monitoring/instrumentation , Radiometry/instrumentation , Space Flight/instrumentation , Forecasting , Mathematics , Plastics , Polyethylene Glycols , Solar Activity
16.
Adv Space Res ; 12(2-3): 349-53, 1992.
Article in English | MEDLINE | ID: mdl-11537028

ABSTRACT

We present measurements of LET spectra for near earth orbits with various inclinations and altitudes. A comparison with calculated LET spectra shows that the contribution from direct ionizing galactic cosmic rays is well described by the models. An additional contribution to the spectra originates from stopping protons and from nuclear interactions of particles with material. In the case of an interaction a large amount of energy is deposited in a small volume by target recoils or target fragments. These events will be called short range (SR) events. For a low inclination orbit radiation belt protons are the main source of these events while galactic protons become more important when increasing the inclination to near polar orbits. We show that the contribution of SR events for orbits with low altitude (324 km) and 57 degrees inclination is comparable to that for an orbit with 28 degrees inclination at a high altitude (510 km).


Subject(s)
Cosmic Radiation , Linear Energy Transfer , Models, Theoretical , Radiation Monitoring/statistics & numerical data , Space Flight , Extraterrestrial Environment , Protons , Radiation Protection/statistics & numerical data
17.
Int J Rad Appl Instrum D ; 20(1): 75-100, 1992 Jan.
Article in English | MEDLINE | ID: mdl-11537534

ABSTRACT

The long duration exposure facility (LDEF), launched into a 258 nautical mile orbit with an inclination of 28.5 degrees, remained in space for nearly 6 yr. The 21,500 lb NASA satellite was one of the largest payloads ever deployed by the Space Shuttle. LDEF completed 32,422 orbits and carried 57 major experiments representing more than 200 investigators from 33 private companies, 21 universities and nine countries. The experiments covered a wide range of disciplines including basic science, electronics, optics, materials, structures and power and propulsion. A number of the experiments were specifically designed to measure the radiation environment. These experiments are of specific interest, since the LDEF orbit is essentially the same as that of the Space Station Freedom. Consequently, the radiation measurements on LDEF will play a significant role in the design of radiation shielding of the space station. The contributions of the various authors presented here attempt to predict the major aspects of the radiation exposure received by the various LDEF experiments and therefore should be helpful to investigators who are in the process of analyzing experiments which may have been affected by exposure to ionizing radiation. The paper discusses the various types and sources of ionizing radiation including cosmic rays, trapped particles (both protons and electrons) and secondary particles (including neutrons, spallation products and high-LET recoils), as well as doses and LET spectra as a function of shielding. Projections of the induced radioactivity of LDEF are also discussed.


Subject(s)
Elementary Particles/classification , Radiation Monitoring/instrumentation , Radiation, Ionizing , Space Flight/instrumentation , Computer Simulation , Cosmic Radiation , Linear Energy Transfer/radiation effects , Magnetics , Radiation Monitoring/statistics & numerical data , Radiation Protection/instrumentation , Radiation Protection/statistics & numerical data , Solar System , Spacecraft
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