Published 1999
| Version v1
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Determination of the neutron flux characteristics and personal dose equivalents in the Thermal Column of the SAR-Graz
Creators
- 1. Inst. fuer Theoretische Physik, Technische Univ. Graz (Austria)
Description
It was the aim of this work to test the general-purpose Monte Carlo Neutron Particle code MNCP 4B and the different cross-section data in the low neutron energy region by using the Thermal Column of the research reactor SAR (Siemens Argonaut Reactor) in Graz-Austria. The paper demonstrates the application potential of the modern particle transport code MCNP 4B in determining the neutron field characterized by the energy and angular distribution of the neutron flux density, and in solving neutron dosimetry problems in the Thermal Column (TC).(author)
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33071076.pdf
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Additional details
Publishing Information
- Publisher
- Nuclear Society of Slovenia
- Imprint Place
- Ljubljana (Slovenia)
- ISBN
- 961-6207-13-X
- Imprint Title
- International Conference Nuclear Energy in Central Europe 99, V. 1. Proceedings
- Imprint Pagination
- 683 p.
- Journal Page Range
- p. 665-671
- Report number
- INIS-SI--02-002
Conference
- Title
- International Conference on Nuclear Energy in Central Europe 99
- Dates
- 6-9 Sep 1999
- Place
- Portoroz (Slovenia)
INIS
- Country of Publication
- Slovenia
- Country of Input or Organization
- Slovenia
- INIS RN
- 33071076
- Subject category
- S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CALCULATIONS; M CODES; MONTE CARLO METHOD; NEUTRON DOSIMETRY; NEUTRON FLUX; NEUTRON TRANSPORT; STARK REACTOR
- Descriptors DEC
- ARGONAUT TYPE REACTORS; CALCULATION METHODS; COMPUTER CODES; DOSIMETRY; ENRICHED URANIUM REACTORS; NEUTRAL-PARTICLE TRANSPORT; RADIATION FLUX; RADIATION TRANSPORT; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS; TRAINING REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 6 refs., 6 figs.