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USE OF THE REACTORS IN FORTENAY-AUX-ROSES FOR STUDY OF SHIELDING PROBLEMS (in French)

Journal Article · · Atompraxis (West Germany) Incorporated in Kerntechnik
OSTI ID:4735527
It is explained why it is important, in designing a reactor, to know the radiation level in the various shielding layers. Before the shielding can be calculated with sufficient accuracy, these factors must be theoretically understood; the effective differential cross sections for elastic and inelastic interactions must also be known much better than they are at present. Since present theories are not yet certain, and serve mainly as guide-lines for experimental studies, model tests play an important part in radiationprotection research. Considerations governing the choice of particular experimental equipment and the equipment are described. The first experiments were made with Zoe, a natural uranium heavy-water reactor with an output of 150 kw and a 90-cm graphite reflector. In 1954 the construction of the experimental unit Naiade I was decided upon. A sheet of natural uranium with a surface of 1 m/sup 2/ and a thickness of 2 cm was bombarded with thermal neutrons from Zoe. The zone in which fission takes place can be determined by screening the neutron beam. Measurement of effective cross sections and test measurement of models can be made under water in an aluminium container. The planning and execution of the tests made with these two installations are closely described, as well as those made with Triton I, a swimming-pool reactor (18.30 x 6.00 x 9.95 m) with an output of 1 to 2 Mw. Triton I was designed for radiation-protection studies and can be used for largesized test objects. The reactor Triton II and the attachment unit Naiade II, with their instrumentation, and with test models are described. (auth)
Research Organization:
Centre d'Etudes Nucleaires, Fontenay-Aux-Roses, France
NSA Number:
NSA-17-019588
OSTI ID:
4735527
Journal Information:
Atompraxis (West Germany) Incorporated in Kerntechnik, Journal Name: Atompraxis (West Germany) Incorporated in Kerntechnik Vol. Vol: 9; ISSN ATPXA
Country of Publication:
Country unknown/Code not available
Language:
French