[en] Intermediate neutrons form an important part of the neutron-tissue dose outside the reactor shielding. Equipment developed in the RUS series makes it possible to measure the flux and the tissue dose rate of intermediate neutrons. In experiments on the 1RT-1000 reactor the neutron-dose composition was studied and it was shown that this depends greatly on the composition of the shielding. It was found that the neutron-tissue dose calculated from data obtained by means of RPN-1 apparatus is in reality too low by a factor of up to 1.5 for water shielding and 5 for concrete shielding. (author)
[fr]
Les neutrons intermédiaires contribuent de façon, appréciable à la dose tissulaire de neutrons derrière l*écran d'un réacteur. On a mis au point des instruments de la série ROUS qui permettent de mesurer la densité et la puissance de la dose tissulaire de neutrons intermédiaires. Au cours des expériences dans le réacteur IRT-1000, les auteurs ont mesuré la composition dosimétrique des neutrons et montré qu'elle dépend dans une large mesure de la nature de l'écran. On a établi que la dose tissulaire de neutrons calculée sur la base des données fournies par l'instrument RPN-1 doit être en réalité diminuée d'un facteur de 1,5 derrière un écran d'eau et de 5 derrière un écran de béton. (author)[es]
Los neutrones intermedios contribuyen significativamente a la dosis tisular neutrónica fuera del blindaje del reactor. Los autores perfeccionaron una serie de instrumentos de la serie RUS que permiten medir el flujo y la intensidad de la dosis tisular de neutrones intermedios. Aplicándolos a una serie de experimentos en el reactor IRT-1000, analizaron la composición dosimétrica de los neutrones y comprobaron que depende en gran medida del material de blindaje. Establecieron que la dosis neutrónica tisular, -calculada partiendo de las indicaciones del dosímetro individual RPN-1, disminuye efectivamente en una proporción que alcanza a 1,5 para el blindaje de agua y a 5,0 para el de hormigón. (author)[ru]
Promezhutochnye nejtrony dajut sushhestvennyj vklad v tkanevuju do zu nejtronov za zashhitoj reak tora. Razrabotany pribory serii RUS , pozvoljajushhie izmerit' potok i moshhnost' tkanevoj dozy promezhutochnyh nejtronov. V jeksperimentah na reaktore IRT-1000 issledovan doznyj s o stav nejtronov i pokazano, chto sushhestvenno zavisit ot sostava zashhity. Ustanovleno, chto tkanevaja doza nejtronov, vychislennaja po pokazanijam pribora RP N -1 , v dejstvitel'nosti zanizhaetsja na kojefficient, dostigajushhij 1,5 za vodjanoj zashhitoj i 5 za betonnoj zashhitoj. (author)Source
International Atomic Energy Agency, Vienna (Austria); 448 p; Mar 1964; p. 129-140; Symposium on Biological Effects of Neutron Irradiations; Upton, NY (United States); 7-11 Dec 1963; IAEA-SM--44/56; ISSN 0074-1884; 
; 13 refs., 2 tabs., 4 figs.
; 13 refs., 2 tabs., 4 figs.
[en] In an MR reactor performance tests of 16 fuel assemblies, with elements having essentially the same structure as standard VVER-100 fuel elements, were carried out. Tests of five more fuel assemblies are continuing. Of the 16 assemblies, 13 were studied in a hot laboratory. The test in the MR, carried out at high loads and with a large number of transition processes, as well as the postreactor studies, indicated the fuel elements of the specified design (with initial helium pressures of 1.96-2.45 MPa) have a high reliability. None of the elements of the fuel assemblies studied malfunctioned due to design defects or faults in their fabrication. During the tests the jackets were subject to a little oxidation and hydrogenation (zirconium-oxide film < μm thick, hydrogen content less than 0.008% by mass), and their plasticity remained high (the relative elongation at the working temperature remained at the 20% level)
Journal
[en] The experience of using the neutron radiography method for the nondestructive testing and investigation of fuel elements of nuclear reactors is reported. The neutron radiography facility constructed on the basis of the vertical channel of the MR-type reactor is described. Practical results of using the neutron radiography for analysis of irradiated and nonnirradiated fuel elements are presented. (Auth.)
Source
Barton, J.P. (Neutron Radiography Consulting, La Jolla, CA (USA)); Hardt, P. von der (Commission of the European Communities, Petten (Netherlands). Joint Nuclear Research Center) (eds.); 1090 p; ISBN 90-277-1528-9; ; 1983; p. 375-382; D. Reidel; Dordrecht (Netherlands); 1. World conference on neutron radiography; San Diego, CA (USA); 7-10 Dec 1981
; 1983; p. 375-382; D. Reidel; Dordrecht (Netherlands); 1. World conference on neutron radiography; San Diego, CA (USA); 7-10 Dec 1981