Some modelisation aspects of the instrumental transformation of neutron kinetic energy into electrical impulse amplitude
Description
The differential energy characterisation of neutron emission or fluxes may be called difficult especially when an approach to metrological standards is required. The use of somewhat complex computing programmes is unavoidable here since the process of selective detection and interpretation of measurement results involves: - Firstly of need to simulate by so-called MONTE CARLO techniques the responses of the various kinds of detector used (the detector responses are so dependent on changes in the environment that experimental calibration -too expensive to be easily repeated from one situation to the next- cannot be recommended); - secondly the need to answer pratically (in a discretized situation by matrix manipulations) to the problem, theoretically without a unique analytical solution, of resolving a Fredholm equation of the first kind. For the understanding, use and as necessary modification of the appropriate codes it is most important to have a very precise conceptual view of the mechanisms involved (in the sequence of direct instrumental transformations). For didactic purposes the present article attempts in a very simple case to give an idea, at increasing levels of complexity: stylisation, schematisation, modelisation, simulation, of the successive stage (neutron-proton energy transfer, analog conversion of ionising particle energy into electric impulse signal size) involved in the formation and understanding of an energy spectrum of recoil nuclei. All these instrumental distortions are made explicit in a kind of underlying two-dimensional ''density''; in its discretized form this is called the instrumental transfer matrix and its understanding and treatment are the ''keys'' to the deconvolution of the recorded spectrum, giving access to the differental distribution of the emitted neutron energies
Availability note (English)
MF available from INIS under the Report Number.Abstract (French)
La caracterisation energetique differentielle d'emissions ou de flux de neutrons peut etre qualifiee de difficile surtout lorsque l'on souhaite qu'elle tende vers la qualite metrologique. L'utilisation de programme de calcul d'une certaine complexite y est incontournable. En effet, dans le processus de detection selective et d'interpretation des resultats de mesurages, il intervient d'une part, la necessite de simuler par des techniques dites de MONTE CARLO, les reponses des detecteurs de types divers utilises (les reponses des detecteurs sont, a ce point dependantes des modifications dans l'environnement que l'etalonnage experimental trop couteux pour etre facilement renouvele selon les situations ne peur etre recommande); d'autre part l'obligation de repondre pratiquement (dans une situation discrete par manipulations matricielles) au probleme (theoriquement sans solution analytique unique) de la resolution d'une equation de Fredholm de premiere espece. Le present texte cherche a donner, dans un cas des plus simples, une idee (a des niveaux de complexite croissante: stylisation, schematisation, modelisation, simulation) des etapes (transfert energetique neutron-proton, transformation analogique d'energie de particule ionisante en taille de signal impulsionnel electrique) qui se succedent dans la formation et l'apprehension d'un spectre d'energie de noyaux de recul. L'ensemble de ces distorsions instrumentales se trouve explicite dans une sorte de ''densite'' bidimensionnelle sous-jacente que sous sa forme discretisee on appelle matrice de transfer instrumentale et dont la comprehension et le traitement sont les ''clefs'' de la deconvolution du spectre releve en vue de remonter a la distribution differentielle des energies de neutrons emisFiles
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Additional details
Additional titles
- Original title (French)
- Quelques aspects de modelisation d'une transformation instrumentale d'energie cinetique de neutron en amplitude d'impulsion electrique
Publishing Information
- Imprint Pagination
- 69 p.
- Report number
- CEA-N--2410
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 16025912
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Descriptors DEI
- DIFFERENTIAL CROSS SECTIONS; ENERGY TRANSFER; MONTE CARLO METHOD; NEUTRON DETECTION; NEUTRON FLUX; NEUTRON SOURCES; NEUTRON SPECTROSCOPY; RESPONSE FUNCTIONS; TRANSFER MATRIX METHOD
- Descriptors DEC
- CROSS SECTIONS; DETECTION; FUNCTIONS; PARTICLE SOURCES; RADIATION DETECTION; RADIATION FLUX; RADIATION SOURCES; SPECTROSCOPY