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PNC TN9410 96-235, 258 Pages, 1996/03
The chemical decontamination technique has been developed in order to remove the crud adhering to the surface of the components constructing the primary coolant system, as a part of the measure to decrease the exposure in the annual inspection. The technique has been already applied to the prototype reactor "Fugen", in the core of which the fuel assemblies were not loaded. The chemical decontamination, for the core in which the fuel assemblies are loaded, has been planned for the purpose of improving the utilization factor. It is necessary to confirm, through the test before putting the plan into practice, that the decontamination reagent does not exert a bad influence upon the components constructing the fuel assembly. This report describes the test results which have been carried out so as to investigate the influence of the reagent on the components constructing the fuel assembly. The outline of the results is as follows: (1)The susceptibility to stress corrosion cracking of the chemical decontamination treatment and the residual decontamination reagent on the components constructing the fuel assembly is low enough. (2)The chemical decontamination treatment and the residual decontamination reagent do not exert a bad influence upon the integrity of the fuel assembly concerning the fuel rod holding function of the spacer and the characteristics of the fretting wear caused on the fuel claddings.
Muramatsu, Toshiharu; Murata, Masayuki*; Ieda, Yoshiaki; Yamaguchi, Akira; Nagata, Takashi; Sugawara, Satoru
PNC TN9410 91-318, 48 Pages, 1991/10
In-vessel thermohydraulic analysis with multi-purpose three-dimensional code AQUA as conducted for transient simulating a pump coast down and reactor scram (manual reactor trip event) to confirm efficiency of partially dip plate equipments in a large-scale fast breeder reactor. Throught the analysis using the AQUA code and the discussion based on their results, the following results have been obtained: [Sodium Surface Velocity] Maximum surface velocity is 0.33m/s in the condition of D=0.75m and W=1.905m. The velocity is the same as that or the MONJU reactor. [Thermal Stratification] Maximum axial temperature gradient 445
C/m was calculated. The gradient is nearly equal to the results in the MONJU reactor. [Main Loop Temperature Transient] Maximum temperature transients at the outlet nozzle of reactor vessel was -0.51C/s. [Circumferential Temperature Gradient] Maximum circumferential temperature gradient at the neighborhood of reactor vessel was 67C/m. The gradient is equivalent to five times of that when a partially dip plate is not adopted.
; *; ; Yamaguchi, Akira; ; Sugawara, Satoru
PNC TN9410 91-089, 130 Pages, 1991/03
In-vessel thermohydraulic analysis with multi-dimensional code AQUA was conducted for transient simulating a pump coast down and reactor scram (manual reactor trip event) to confirm efficiency of outer barrel equipments on a large-scale fast breeder reactor. Through the analysis using the AQUA code and the discussion based on their results, the following results have been obtained: [Main Loop Temperature Transient] The transient rate with the outer barrel equipments are approximately equal to the result when an inner barrel was adopted. [Thermal stratification] Axial temperature distributions are approximately equal to the result in the case without an inner barrel. Therefore appearance of an axial temperature distribution can be neglected from a structural design. [Circumferential Temperature Distribution] Maximum temperature gradient 104C/m was confirmed. The value is equivalent to three times of that when an inner barrel was not adopted. Further investigation on a thermal stress at reactor vessel is necessary. [Sodium Surface Velocity] Maximum velocity is the same as that described for the case without an inner barrel. From the above results, it is concluded that the outer barrel considered here is an efficient equipment to relax the main loop temperature transient.
; ; Araki, Masanori; ; ; ; ; ; Matsuda, Shinzaburo; ; et al.
Review of Scientific Instruments, 55(3), p.332 - 337, 1984/00
Times Cited Count：19 Percentile：86.94(Instruments & Instrumentation)no abstracts in English
; ; ; ; ; ; *; Ohara, Yoshihiro; *; G.L.Jahns*; et al.
JAERI-M 9181, 27 Pages, 1980/11
no abstracts in English
*; ; ; G.L. Jahns*; ; ; *;
JAERI-M 9180, 8 Pages, 1980/11
no abstracts in English
; ; *; ; ; Ohara, Yoshihiro; ; ; *; ; et al.
JAERI-M 8983, 17 Pages, 1980/08
no abstracts in English
