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; Numata, Kazuyuki*
JNC TN9400 2000-036, 138 Pages, 2000/03
JNC-TN9400-2000-036.pdf:10.16MB
Japan Nuclear Cycle Development lnstitute (JNC) had developed the adjusted nuclear cross-section library in which the results of the JUPITER experiments were renected. Using this adjusted library, the distinct improvement of the accuracy in nuclear design of FBR cores had been achieved. As a recent research, JNC develops a database of other integral data in addition to the JUPITER experiments, aiming at further improvement for accuracy and reliability. ln this report, the authors describe the evaluation of the C/E values and the sensitivity analysis for the Experimental Fast Reactor "JOYO" MK-l core. The minimal criticality, sodium void reactivity worth, fuel assembly worth and burn-up coefficient were analyzed. The results of both the minimal criticality and the fuel assembly worth, which were calculated by the standard analytical method for JUPITER experiments, agreed well with the measured values. 0n the other hand, the results of the sodium void reactivity worth have a tendency to overestimate. As for the burn-up coefficient, it was seen that the C/E values had a dispersion among the operation cycles. The authors judged that further investigation for the estimation of the experimental error will increase the applicability of the integral data to the adjusted library. Furthermore, sensitivity analyses for the minimal criticality, sodium void reactivity worth and fuel assembly worth showed the characteristics of "JOYO" MK-l core in comparison with ZPPR-9 core of JUPITER experiments.
Wada, Hiroaki
JNC TN8400 2000-015, 37 Pages, 2000/03
This report describes the study done within the period of time when I was postdoctoral research worker at Japan Nuclear Cycle Development Institute. The report includes two parts as follows. (1) Exact Solution of Electric Transitions for High Energy photons. Technologies for creating high-energy 
beams have been rapidly developed. These advancements make the research using high-energy -rays more important. The electric transition rates for high-energy -rays were formulated. The electric multipole fields were treated strictly in the process of calculating the electric transition rates and the nuclear states were taken as the harmonic oscillator wave functions. (2) Production of the isomeric state of 
Cs in the thermal neutron capture reaction 
Cs(n, )Cs. In order to obtain precise data of the neutron capture cross section of the reaction Cs(n, )Cs, the production probability of isomer state 
Cs was measured in this work. The 1436 keV -ray emitted from both of 
Cs and Cs was measured. A production ratio of Cs to (Cs and Cs) was deduced from time dependence of peak counts of 1436keV -ray. The probability of the production of CS was obtained as 0.75
0.18 and this value revised the effective cross section upwards 92%. The effective cross section 
and the thermal neutron capture cross section 
were obtained as =0.290.02 b and =0.270.03 b with taking into account the production of 
Cs.
; Kawai, Masashi; ; ; ; Okubo, Toshiyuki;
PNC TN9410 94-094, 69 Pages, 1994/03
As the final step of development of a control rod guide system (rod guider), it has been conducted to display information concerning the rod guider operation and the current plant conditions on a CRT in Japanese, to tell information for operators and to predict more accurately the stroke of each control rod to be driven at a reactor power adjustment operation since 1992, in oder to improve a function of man-machine interface of the rod guider. The development of the rod guider was completed with the following good results as expected. (1)The function of man-machine interface of the rod guider was improved to display information on a CRT in Japanese. (2)The voice guidance contributed to obtain higher operational reliability and to lower the load on the operators. (3)The rod guider provided the same function as operation manuals of Joyo because all operation procedures in the manuals were inputted into the rod guider. And the timely operation guides provided by the rod guider evabled non-skilled operators to control the reactor in the same manner as the experienced ones. (4)The difference of the predicted and actual rod stroke to be driven at the reactor power adjustment operation was reduced to less than 0.2mm by both the existing inverse multiplication method and the experiences gained in the past five reactor power adjustment operations.