Published December 1967 | Version v1
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Thermal neutron flux and heating in the upper thermal shield of a graphite reactor

Creators

Description

The aim of these experiments has been to measure the thermal flux and overheating in the axis of a channel loaded with different geometrical configurations. It has been used as radiation source the Naiade II sub critical stacking, loaded in Inca fuel. Two experiment series have been realised with a 60 cm hole reflector and then with a 120 cm hole one. The code Domino 2 has been used to interpret these different experiments

Availability note (English)

Available from INIS in electronic form

Abstract (French)

Le but de ces experiences a ete la mesure des flux thermiques et des echauffements dans l'axe d'un canal charge, avec differentes configurations geometriques. On a utilise comme source de rayonnement l'empilement sous-critique de Naiade II, charge en combustibles Inca. Deux series d'experiences ont ete realisees, avec un reflecteur troue de 60 cm puis de 120 cm. Pour interpreter ces differentes experiences, on a utilise le Programme Domino 2. (auteurs)

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Additional details

Additional titles

Original title (French)
Flux de neutrons thermiques et echauffement dans le bouclier thermique superieur d'une pile a graphite

Publishing Information

Imprint Pagination
44 p.
Report number
CEA-N--833

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
35044188
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY;
Resource subtype / Literary indicator
Numerical Data
Descriptors DEI
EXPERIMENTAL DATA; GRAPHITE MODERATED REACTORS; NEUTRON FLUX; THERMAL NEUTRONS; THERMAL SHIELDS
Descriptors DEC
BARYONS; DATA; ELEMENTARY PARTICLES; FERMIONS; HADRONS; INFORMATION; NEUTRONS; NUCLEONS; NUMERICAL DATA; RADIATION FLUX; REACTORS; SHIELDS