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; Aoyama, Takafumi; ; Shirakata, Keisho
JNC TN9400 2001-032, 57 Pages, 2001/01
JNC-TN9400-2001-032.pdf:1.53MB
This report describes the reactivity measurement method and its accuracy employed in ZPPR (Zero Power Physics Reactor) test facility at Argonne National Laboratory, USA. In ZPPR, reactivity measurements were conducted by means of MSM (Modified Neutron Source Multiplication) method using the fission reaction rates by 64 
U fission chambers which were uniformly located in the core region. The MSM method can evaluate the subcritical reactivity considering the spatial distribution of neutron flux, although its basic equation is the one point approximation reactor dynamic theory. As each detector response varies depending on the core configuration, the uncertainty of the detector response affect directly the accuracy of measured reactivity. Therefore, the average value of many detectors had been conventionally used to reduce the statistical error in the measurerment. In this study, this method was modified to use the linear fitting between measured reaction rates and detector responses. Using this modified method, the uncertainty of each detector response affect the measured reactivity less than the simple averaging method. This new method was verified by applying to the ZPPR control rod worth measurements. It was found that the ratios of neutron source intensities and detector responses could be corrected accurately by the linear fitting in case of reactivity change without or with little fuel movement such as a unit control rod worth measurement.
Shirakata, Keisho; ; Nakashima, Fumiaki
Nuclear Science and Engineering, 131, p.137 - 198, 1999/00
None
Shirakata, Keisho
PNC TN9410 96-033, 28 Pages, 1996/02
In the U.S.-Japan joint physics large LMFBR core critical experiment program (called JUPITER), neutronic couplings were measured in addition to usual physics characteristics. They were measured particularly in the JUPITER-Io program, whose main purp0se was to study the neutronic decoupling problems. Static, methods such as flux distortions caused by control rod insertion and flux tilt, and dynamic methods such as rod drop, boron oscillator and noise coherence experiments were applied to the measurements of eigenvalue separation, an indicator of the spatial decoupling. Measured results of different methods roughly agreed with each other, and also agreed with calculated results. As a result, it was made clear that the measurement methods were reliable and effective, and that the reactor physics parameter, called eigenvalue separation, could be measured.
Shirakata, Keisho; ; Nakashima, Fumiaki
Nuclear Science and Engineering, 113(2), p.97 - 108, 1993/02
Times Cited Count：8 Percentile：63.68(Nuclear Science & Technology)None
Sanda, Toshio*; *; *
PNC TN9410 89-098, 278 Pages, 1989/06
Physics parameters were evaluated for FBR Cores with new fuels, i.e., metal, carbide and nitride fuels in comparison with the oxide fuel cores. The main results in FY'88 are as follows. (1)Some critical experiments and FBR core designs with new fuels were investigated and reviewed from the view point of nuclear characteristics of the core, For Zr and N cross sections, which are needed for new fuel cores, JENDL-3 library data must be used because these cross sections are not included in JENDL-2 library. (2)Physics parameters were compared between new fuels and oxide fuel cores. The conventional two-zone homogeneous core was selected for the calculation. The four cores were designed to be equal to another in dimension, core configuration, specific power density and peak linear heat rate, Comparisions are summarized as follows. (i)The burn-up reactivity loss is decreased to be nearly zero for the new fuel cores, and the breeding ratio is raiseed by about 0.2 for the new fuel cores compared with the oxide core. (ii)The maximum fast neutron fluence of the metal fuel core is about 30% larger than the oxide core due to harder spectrum and decreased effective fission cross section. (iii)The Na void reactivity and the Doppler coefficient for the metal fuel core are worse than those for the oxide core from the safety point of view, but reactivity coefficients due to fuel axial and radial expansion becomes more negative, (3)Cross section sensitivity analyses were conducted and uncertainties of core parameters due to cross section uncertainties were evaluated using cross section sensitivities and covariances. It was made clear that their total sensitivities to individual cross sections, except oxygan, were not very much different between the metal and oxide fuel core, though 100KeV
1MeV sensitivities for the metal are larger than those for the oxide fuel core. The uncertainties of core parameters due to cross section uncertainties are almost equal for the ...
*; *; *; 7 of others*
PNC TN2410 89-003, 349 Pages, 1989/03
The works of JUPITER sub-working group in FT'88 are summarized in this report. JUPITRR-III program is the co-operative research program between PNC and DOE, using ZPPR in ANL-W. The JUPITER sab-working group is organized by the reactor physics group of Reactor Research and Development Project, PNC, for planning and analysis of the experiment in JUPITER-III program. The first half of the JUPITER-III program, the ZPPR-17 program, was physics benchmark experiments to study the neutronic behavior of a 650 MWe-size, axially heterogeneous LMR core. The second half of the program, the ZPPR-18 program, was 1000 MWe-size two-zone homogeneous cores. ZPPR-17 was analysed almost completely, but ZPPR-18 analysis is being prepared. The main results of this year are as follows. (1)The following conclusions were obtained from the ZPPR-17 analysis. (i)In addition to the standard analysis model, the center-line and multi-drawer models were used. The effects on criticality were +0.17% for the former model and +0.080.09% for the latter model. The C/E values were almost the same as those for ZPPR-9 and ZPPR-13A. (ii)The C/E values were about 0.9 at the core center, and became about 5% higher at the core edge. The similar radial variations of C/E were observed in reaction rate distributions. The magnitude of 510% in the mispredictions are consistent with the previous values obtained in the analysis of the homogeneous core. (iii)The C/E values of sodium void reactivities were about 1.21.5 for the core regions, and about 0.8 for the internal blanket regions. The C/E values of sample reactirities in the internal blanket region were smaller than those in the core region by about 20% for 
Pu sample and by about 10% for 
B sample. The same underprediction in the internal blanket region was also seen in ZPPR-13A. (2)An attempt was made for building a data base system for the JUPITER program using the ZPPR-17A experimental data as an example. Some ...
Shirakata, Keisho; Yamamoto, Toshihisa
Donen Giho, (67), p.76 - 78, 1988/09
None
Shirakata, Keisho; Nakashima, Fumiaki; Sanda, Toshio*; *; Kawashima, Masatoshi*; *; *
PNC TN2410 88-004, 359 Pages, 1988/03
The JUPITER-III program, which started in Jan. 1987, successfully ended after one year experimental period without any delay from the original schedule. In the study last year, we mainly proceeded the experimental planning checks and data arrangement. This time studies were done putting an emphasis on the analysis of the experimental data and following conlusions were derived from the studies. (1)Pre-analysis for ZPPR-18 was done attempting to check the experimental plan. The result was actually reflected to the experiments for ZPPR-18 successfully. (2)Analysis of criticality for ZPPR-17A, 17B and 17C was done. The C/E value 1.0003 for ZPPR-17A comes to be almost the same value as that for ZPPR-9, which is 0.9995. (3)
evaluation was made for ZPPR-17A and ZPPR-17B. The value obtained in this study is higher by 3 % than that of ANL, which shows the same tendency as found in the JUPITER-I and II analyses. (4)Control rod calculations were done for ZPPR-17A and 17B. The following C/E values were obtained as a result. Plate type control rod : 0.8710.899. Pin type control rod : 0.8830.890. (5)Experimental data arrangement was done for large zone sodium void experiments and for sodium void drawer oscillating experiments. (6)Criticality analysis for ZPPR-12 was performed for the pin cores and the plate Cores. The C/E value for central and edge pin zone cores agreed with those for the plate cores as shown bellow. Central pin : 1.018. Edge pin : 1.019. Plate cores : 1.020 (7)An attempt was made for building a data base system for the JUPITER programs, using the ZPPR-17A experimental data as an test example. (8)Multidrawer effect was evaluated for ZPPR-17A. The effect on criticality is +0.17
k/k.
Shirakata, Keisho
Proceedings of International Conference on Nuclear Data for Science and Technology (ND 1988), p.53 - 56, 1988/00
None
*; Sanda, Toshio*; *
PNC TN2410 87-006, 291 Pages, 1987/05
JUPITER-III program (a joint study between PNC and DOE) was started in order to obtain informations required for designs of large LMFBR cores. Experimental plans, experimental data arrangement and their preliminary analyses were carried out, and the following results were obtained. (1) Final experimental plans were determined for the first axial heterogeneous core ZPPR-17A on Japanese proposed plans through the meeting between PNC and ANL. The experiments in the ZPPR-17A Assembly have completed as proposed. (2) The analysis models suitable for JUPITER-III were selected. Detailed analysis models for cell heterogeneity and so on were also discussed. C/E value of k for ZPPR-17A (AHC) is lower than that of ZPPR-9 (HOC) by about 0.1%. (3) Information for the ZPPR-12 and ZPPR-13D experiments, which were supplementally provided from ANL to JUPITER-III program, were investigated from the points of the design studies. No large discrepancies were found in the pin-plate biases in the first analysis of the criticality of the ZPPR-12 series. The magnitude of the discrepancy in the pin-plate bias was 0.1%k in the present analysis. Present results showed different tendency in the biases for the criticality from the results obtained in the international benchmark calculations for the CADENZA programs. (4) The results of JUPITER-I, II and FCA experiments and their analyses were assessed from the standpoints of the planning of JUPITER-III program and their analyses.
Shirakata, Keisho; Koizumi, Masumichi*; *; *; *; *
Genshiryoku Kogyo, 31(8), p.43 - 65, 1985/08
*; *; *; *; Matsuno, Yoshiaki*; Mochizuk, Keiichi
PNC TN253 85-01, 119 Pages, 1984/12
no abstracts in English
; ; ;
Nuclear Science and Engineering, 87, p.252 - 261, 1984/00
Times Cited Count：2 Percentile：29.96(Nuclear Science & Technology)no abstracts in English
*; Ishiguro, Yukio*; *; Inagaki, Tatsutoshi*; *; *; *; Kato, Yasuyoshi*; Shirakata, Keisho;
PNC TN241 84-07, 16 Pages, 1982/10
None
Takeda, Toshikazu*; *; *; *; *; *
PNC TN241 82-05, 89 Pages, 1982/03
Detailed analysis of a part of JUPITER Phase I experiments has been performed by taking into account the neutron streaming effect. The effect of neutron leakage in cell calculations was estimated in terms of the albedo collision probability method, and the several reaction rate distributions in x and y directions in ZPPR-9 assembly were analysed. Using the effective group constants preserving reaction rates in a super-cell, we calculated the control-rod worth of pin rods used in ZPPR-10A, and estimated the smearing and transport effects. Direct core calculations were performed by taking into account the heterogeneity in the pin rod drawers and the results were compared with those obtained by using the effective group constants. Further reactivity worths of diluent materials measured in ZPPR-10C were analysed by using transport and diffusion calculations. In the diffusion calculation, the Benoist and the unified diffusion coefficients were used.
; *; *; ;
JAERI-M 9931, 41 Pages, 1982/02
no abstracts in English
JAERI 1270, 42 Pages, 1981/03
no abstracts in English
