Comparison of calculation and measurements of reaction rates in the outer regions of superphenix
- 1. UKAEA Risley (UK)
- 2. CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-lez-Durance (France)
Description
This paper brings together the results of two analyses of the Superphenix start-up measurements in the radial shield. Two different methods of calculation have been used based on SN transport theory (the PROPANE DO formulaire with the BISTRO code) and adjusted diffusion coefficients (the code SNAPSH using ADC method D). The PROPANE DO formulaire was found to give good agreement with the measured thermal flux both in the prediction of radial attenuation and in the reproduction of the axial profile. The ADC method was found to underestimate the attenuation. There were difficulties in reproducing the flux and neutron spectrum at the breeder/shield interface with both methods. This detailed comparison with measured values will assist in the formulation of recommended calculational routes for analysis of fast reactor shielding problems, an example of which has been the proposal of revised uncertainties for the PROPANE DO formulaire
Additional details
Publishing Information
- Publisher
- Societe Francaise pour l'Energie Nucleaire.
- Imprint Place
- Paris (France)
- Imprint Title
- The physics of reactors: operation, design and computation. Volume 1
- Imprint Pagination
- 593 p.
- Journal Page Range
- p. VII.29-VII.38.
Conference
- Title
- Operation, Design and Computation.
- Acronym
- International Conference on the Physics of Reactors
- Dates
- 23-27 Apr 1990.
- Place
- Marseille (France).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 22009916
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ACTIVATION DETECTORS; B CODES; COMPARATIVE EVALUATIONS; EVALUATED DATA; EXPERIMENTAL DATA; GOLD; NEUTRON FLUX; REACTOR START-UP; S CODES; SUPER PHENIX REACTOR; TRANSPORT THEORY
- Descriptors DEC
- BREEDER REACTORS; COMPUTER CODES; DATA; ELEMENTS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EVALUATION; FAST REACTORS; FBR TYPE REACTORS; INFORMATION; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MEASURING INSTRUMENTS; METALS; NEUTRON DETECTORS; NUMERICAL DATA; PLUTONIUM REACTORS; RADIATION DETECTORS; RADIATION FLUX; REACTORS; SODIUM COOLED REACTORS; START-UP; TRANSITION ELEMENTS