Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Dietze, K.
JAERI-Conf 2001-006, p.77 - 83, 2001/03
None
Dietze, K.
JNC TN9400 2001-043, 35 Pages, 2001/02
Sample reactivity measurements performed at the fast-thermal coupled facilities SEG / Germany and STEK / Netherlands have been re-analyzed using the JNC standard route for reactor calculation JENDL-3.2 // SLAROM / CITATION / PERKY. The SEG experiments comprise sample reactivity measurements with the most important stable fission products and structural materials in five reactor configurations with different neutron and adjoint spectra. The shapes of the adjoint spectra have been designed to get high sensitivities to neutron capture or the scattering effect. At the STEK configurations, the neutron spectra had an increasing neutron softness covering a broad energy range. A lot of FP nuclides have been measured. The calculated neutron and adjoint spectra are in good agreement with former results. C/E-values of the central reactivity worth (CRW) of about 90 materials (i,e., FP nuclides, structural materials, and standards) are given for 10 facilities. The C/E-values are compared with results obtained with the competitive European scheme JEF-2.2 // ECCO / ERANOS. For the SEG facilities, a crisscross use of JEF-2.2 with the JNC codes has been performed to get addional information about data and codes.
Dietze, K.
JNC TN9400 99-089, 20 Pages, 1999/11
The integral experiments performed at the Rossendorf fast-thermal coupled reactor RRR/SEG have been reanalyzed using the JNC route for reactor calculation JENDL3.2/SLAROM / CITATION / JOINT / PERKY. The Rossendorf experiments comprise sample reactivity measurements with pure fission products and structural material in five configurations with different neutron and adjoint spectra. The shapes of the adjoint spectra have been designed to get high sensitivities to neutron capture or the scattering effect. The calculated neutron and adjoint spectra are in good agreement with former results obtained with the European route JEF2.2/ECCO/ERANOS. The C/E-values of the central reactivity worths of samples under investigation are given. Deviations in the results of both routes are due to the different libraries, codes, and self-shielding treatments used in the calculations. Results outside of the error are discussed.
Bartlett, D.*; Hertel, N.*; Dietze, G.*; Bordy, J.-M.*; Endo, Akira; Gualdrini, G.*; Pelliccioni, M.*; Ambrosi, P.*; Otto, T.*; Siebert, B.*; et al.
no journal, ,
The routine assessment of radiation exposure is in terms of the protection quantities effective dose and equivalent dose in organs or tissues. These quantities are not measurable. For practical applications in radiological protection operational quantities have been defined for external radiation, which are used for the assessment of values of protection quantities. The present system of operational dose quantities for area and personal monitoring has been defined by ICRU, and has been in use for more than 20 years. Special attention has been paid to some inconsistencies in the application of these quantities, in particular for high-energy radiation fields. An ICRU Committee is reviewing the operational dose quantities for external radiation. Various options to the definitions of the operational quantities and their application are being considered. The presentation analyzes the advantages and disadvantages of the options for a recommendation.
Bartlett, D.*; Dietze, G.*; Hertel, N.*; Bordy, J.-M.*; Endo, Akira; Gualdrini, G.*; Pelliccioni, M.*; Ambrosi, P.*; Siebert, B.*; Veinot, K.*
no journal, ,
The routine assessment of radiation exposure is in terms of the protection quantities effective dose and equivalent dose in organs or tissues. These quantities are not measurable. For practical applications in radiological protection operational quantities have been defined for external radiation, which are used for the assessment of values of protection quantities. The present system of operational dose quantities for area and personal monitoring has been defined by ICRU, and has been in use for more than 20 years. Special attention has been paid to some inconsistencies in the application of these quantities, in particular for high-energy radiation fields. An ICRU Committee is reviewing the operational dose quantities for external radiation. Various options to the definitions of the operational quantities and their application are being considered. The presentation analyzes the advantages and disadvantages of the options for a recommendation.
Bartlett, D.*; Dietze, G.*; Hertel, N.*; Bordy, J.-M.*; Endo, Akira; Gualdrini, G.*; Pelliccioni, M.*; Ambrosi, P.*; Siebert, B.*; Veinot, K.*; et al.
no journal, ,
The ICRU operational quantities for area and personal monitoring have been in use for more than 20 years and are currently under review by an ICRU committee. Special attention has been given to inconsistencies in the application of these quantities and the relationship of the existing operational quantities to the newly released ICRP116 conversion coefficients for equivalent dose and effective dose. Previously reference values of these quantities were computed using the kerma approximation for photons and neutrons incident on the ICRU phantom. The kerma approximation is not applicable when the range of secondary charged particles in the phantom is greater than the depth at which the absorbed dose is being computed. Various options in the definitions of the operational quantities and their application are being considered. The current status of the report will be presented in light of the special consideration that is required to minimize the impact on radiation monitoring practice.
Hertel, N. E.*; Bartlett, D. T.*; Dietze, G.*; Bordy, J.-M.*; Endo, Akira; Gualdrini, G.*; Pelliccioni, M.*; Ambrosi, P.*; Siebert, B. R. L.*; Veinot, K.*; et al.
no journal, ,
The International Commission on Radiation Units and Measurements (ICRU) defines a set of operational quantities for use in radiation measurements that provides assessment of the protection quantities recommended by International Commission for Radiological Protection (ICRP). The ICRU operational quantities in current use was defined about 30 years ago. ICRU Report Committee 26 has examined the rationale for operational quantities taking into account the changes in the definitions of the protection quantities and the changes in the fields of application of the operational quantities and protection quantities. The considerations have included the range of types and energies of particles contributing to doses to workers and members of the public. The relationship of the existing recommended operational quantities to the protection quantities has been investigated, as has the impact of changes in routine measurement practice, including instrument design and calibration. The committee has proposed a set of operational quantities which differs from the previous quantities. The major change in the proposed set of quantities is the redefinition of the operational quantities for area monitoring from doses computed at a depth in the ICRU sphere to ones based on particle fluence and the relationship to the protection quantities, effective dose, and equivalent dose to the lens of the eye, and local skin.
