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AbstractAbstract
[en] The only calculational model recognised by the Nuclear Regulatory Commission (NRC) for hot particle dosimetry is VARSKIN Mod 1. Because the code was designed to calculate skin dose from distributed skin contamination and not hot particles, it is assumed that the particle has no thickness and, therefore, that no self-absorption occurs within the source material. For low energy beta particles such as those emitted from 60Co, a significant amount of self-shielding occurs in hot particles and VARSKIN Mod 1 overestimates the skin dose. In addition, the presence of protective clothing, which will reduce the calculated skin dose for both high and low energy beta emitters, is not modelled in VARSKIN Mod 1. Finally, there is no provision in VARSKIN Mod 1 to calculate the gamma contribution to skin dose from radionuclides that emit both beta and gamma radiation. The computer code VARSKIN Mod 1 has been modified to model three-dimensional sources, insertion of layers of protective clothing between the source and skin, and gamma dose from appropriate radionuclides. The new code, VARSKIN Mod 2, is described and the sensitivity of the calculated dose to source geometry, diameter, thickness, density, and protective clothing thickness are discussed. Finally, doses calculated using VARSKIN Mod 2 are compared to doses measured from hot particles found in nuclear power plants. (author)
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Source
Skin dosimetry - radiological protection aspects of skin irradiation workshop; Dublin (Ireland); 13-15 May 1991; EUR--14092; CONTRACT 17794
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AbstractAbstract
No abstract available
Original Title
Implantacao do programa VISCO
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Instituto de Engenharia Nuclear, Rio de Janeiro (Brazil); 175 p; 1981; p. 171; Published in summary form only.
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Miscellaneous
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Williams, D.A.
UKAEA Atomic Energy Establishment, Winfrith (UK). Safety and Engineering Science Div1989
UKAEA Atomic Energy Establishment, Winfrith (UK). Safety and Engineering Science Div1989
AbstractAbstract
[en] A long-standing issue in the calculation of aerosol transport phenomena is the treatment of gravitational sedimentation in volumes which have no real settling surfaces. The VICTORIA primary circuit computer code has been extended to model inter-volume settling, and has been used to evaluate the importance of this mechanism for Marviken test 2b. The main conclusion of this study is that the neglect of inter-volume settling may result in the distortion of predicted deposition profiles and aerosol size distributions under certain conditions. These errors in the predicted aerosol behaviour may then give rise to further complications downstream. The results of the VICTORIA calculations are in good agreement with the data from test 2b. (author)
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Apr 1989; 30 p
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Report
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AbstractAbstract
[en] A new technique for estimating the magnitude of the chord-averaged plasma electron temperature is described, permitting improved time resolution. A CAMAC software package VEKTOR has been developed to implement this algorithm. The measuring circuit has been checked in a test system for input voltages up to 400 kHz from a spectrometric signal simulator. The operating system is controlled by an IBM PC/AT. The program is constructed using standard routines. It includes an asynchronous data acquisition package, a universal parallel program interpreter, a menu of processing programs, and data visualization. The software runs under MS-DOS (version 3.3). 1 ref., 3 figs
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Cover-to-cover Translation of Fizika Plazmy (USSR); Translated from Fiz. Plazmy; 18: No. 2, 231-234(Feb 1992).
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Journal Article
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Translation
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AbstractAbstract
[en] This paper describes the main features of VENTRAD, a computer program which models radon-related contamination in mine airways. Used in conjunction with a conventional mine ventilation network analysis program which establishes a flow distribution, the program clearly illustrates a number of features concerning radon-related contamination which are not obvious from the application of radon growth theory to individual airways. The inter-relation of contamination levels in various airways under different ventilation strategies may be studied. It is possible to simulate point sources of contamination and the effects of leakage and short-circuiting of air currents
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Source
Stocker, H. (ed.); Canadian Nuclear Association, Toronto, ON (Canada); 704 p; 1985; v. 2 p. 456-462; Occupational radiation safety in mining; Toronto, ON (Canada); 14-18 Oct 1984
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Miscellaneous
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Related RecordRelated Record
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AbstractAbstract
[en] The computer code, VAHAK, provides the required information for the consignor and carrier of radioactive consignments. The output of this code gives information on the classification of the radioactive materials, as per the regulatory requirements. The code is written in interactive mode and demands the input data required, to be supplied by the user. (author). 1 fig., 2 tabs
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18. annual conference of IARP [Indian Association for Radiation Protection]; Tarapur (India); 14-16 Feb 1991
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Journal Article
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Conference
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Jung, Woo Sik; Suh, Jae Seung
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2010
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2010
AbstractAbstract
[en] The purposes of this report are (1) to perform a Verification and Validation (V and V) test for the VIPEX(Vital-area Identification Package EXpert) software and (2) to improve a software quality through the V and V test. The VIPEX was developed in Korea Atomic Energy Research Institute (KAERI) for the Vital Area Identification (VAI) of nuclear power plants. The version of the VIPEX which was distributed is 3.2.0.0. The VIPEX was revised based on the first V and V test and the second V and V test was performed. We have performed the following tasks for the V and V test on Windows XP and VISTA operating systems: Ο Testing basic functions including fault tree editing Ο Testing all kind of functions Ο Research for update from Visual BASIC 6.0 to Visual BASIC 2008
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Jun 2010; 44 p; Also available from KAERI
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Report
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AbstractAbstract
[en] Published in summary form only
Original Title
Codigo Vari-1D
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Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil); 279 p; 1984; p. 26-27
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Miscellaneous
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AbstractAbstract
[en] This book describes theory and practice of VHDL in easy way. It starts introduction of HDL, the design process with VHDL, the constitution of VHDL code, design structure of CHDL, basics for using of VHDL, language grammar of VHDL, design of combinational circuit, synchronizing circuit and asynchronizing circuit design, finite state machine, using of Quartus, parity, 7-segment decode, 4bit adder, 4 X I multiplexer, I X 4 demulitplexer, duodecimal counter, a second counter, LED sequential switch and a traffic signal controller.
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Jun 2006; 283 p; Publishing Company, Green; Seoul (Korea, Republic of); ISBN 89-5727-033-7;
; 4 refs, 73 figs, 4 tabs

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Book
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Marbach, G.
CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France). Dept. de Developpement des Elements Combustibles1979
CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France). Dept. de Developpement des Elements Combustibles1979
AbstractAbstract
[en] The VULKIN code gives the evolution of stresses and strains distribution in the thickness of the clad with the hypothesis of revolution symmetry. This programm takes into account temperature dilatation and radial thermal gradient, fission gas pressure and steel swelling due to neutron flux
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Source
1979; 4 p; IWGFR specialist meeting on fuel modelling; Fontenay-aux-Roses, France; 28 May - 1 Jun 1979
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Report
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