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Harada, Hideo
Kaku Deta Nyusu (Internet), (129), p.35 - 43, 2021/06
This paper explained the activities of the International Nuclear Data Evaluation Co-operation (WPEC)'s subgroup SG-41, which was carried out to improve the accuracy of nuclear data. In this paper, by focusing on how to deal with discrepant data, the method of deriving recommended values from multiple measurement results was reviewed. It also explained how to derive the recommended values, including exercises.
2000/12)Kobayashi, Hideo; ; ; ; ; *; *
JNC TN8440 2001-005, 33 Pages, 2001/02
JNC-TN8440-2001-005.pdf:1.24MB
Four mass spectrometers are used for plutonium and uranium isotopic composition analysis in the Plutonium Fuel Center. Analytical errors of the analysis was evaluated based on routine control data obtained with measurement of reference materials. It was confirmed that the errors satisfied the International Target Values for safeguard analysis, and the random error of the analysis was improved by changing conventional method to total evaporation method.
; 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.
Ijiri, Yuji; ;
JNC TN8400 99-091, 69 Pages, 1999/11
It is crucial for the performance assessment of geosphere to evaluate the characteristics of fractures that can be dominant radionuclide migration pathways from a repository to biosphere. This report summarizes the charactelistics of fractures obtained from broad literature surveys and the fields surveys at the Kamaishi mine in northern Japan and at outcrops and galleries throughout the country. The characteristics of fractures described in this report are fracture orientation, fracture shape, fracture frequency, fracture distribution in space, transmissivity of fracture, fracture aperture, fracture fillings, alteration halo along fracture, flow-wetted surface area in fracture, and the correlation among these characteristics. Since granitic rock is considered the archetype fractured media, a large amount of fracture data is available in literature. In addition, granitic rock has been treated as a potential host rock in many overseas programs, and has JNC performed a number of field observations and experiments in granodiorite at the Kamaishi mine. Therefore, the characteristics of fractures in granitic rock are qualitatively and quantitatively clarified to some extent in this report, while the characteristics of fractures in another rock types are not clarified.
Yui, Mikazu; ; Shibata, Masahiro
JNC TN8400 99-070, 106 Pages, 1999/11
This report is a summary of status, frozen datasets, and future tasks of the JNC thermodynamic database (JNC-TDB) for assessing performance of high-level radioactive waste in geological environments. The JNC-TDB development was carried out after the first progress report on geological disposal research in Japan (H3). In the development, thermodynamic data (equilibrium constants at 25 
C, I=0) for important radioactive elements were selected/determined based on original experimental data using different models (e.g., SIT, Pitzer). As a result, the reliability and traceability of the data for most of the important elements were improved over those of the PNC-TDB used in H-3 report. For detailed information of data analysis and selections for each element, see the JNC technical reports listed in this document.
; *
JNC TN9450 2000-002, 335 Pages, 1999/10
JNC-TN9450-2000-002.pdf:21.65MB
This report summarizes the material test dala of SUS304 welded joints. Numbers of the data are as follows: [Tensile tests 71 (Post-irradiation: 39, others: 32) [Creep tests 77 (Post-irradiation: 20, others: 57) [Fatigue tests 50 (Post-irradiation: 0) [Creep-fatigue tests 14 (Post-irradiation: 0) This report consists of the printouts from "the structural material data processing system".
Ishikawa, Kiyoshi*; Mezaki, Yoshihiko*; Suzuki, Hideo*; Kai, Masanori*; Watanabe, Hajime*; Fujimori, Seiji*; Ishikawa, Junichi*
JNC TJ7420 99-016, 878 Pages, 1999/06
no abstracts in English
Tsujimura, Norio; Shinohara, Kunihiko; Momose, Takumaro
PNC TN8410 98-083, 20 Pages, 1998/05
None
Power Reactor and Nuclear Fuel Development Corporation
PNC TN9360 95-002, 98 Pages, 1995/11
no abstracts in English
Power Reactor and Nuclear Fuel Development Corporation
PNC TN9360 95-001, 104 Pages, 1995/11
no abstracts in English
Power Reactor and Nuclear Fuel Development Corporation
PNC TN9360 94-002, 100 Pages, 1994/02
no abstracts in English
Power Reactor and Nuclear Fuel Development Corporation
PNC TN9360 94-001, 95 Pages, 1994/02
no abstracts in English
Murakami, Kiyonobu*; *
PNC TJ1500 93-004, 114 Pages, 1993/09
no abstracts in English
*
PNC TN9410 93-010, 502 Pages, 1992/12
The present report compiles the experimental data of JUPITER phase-I, which was a joint research program between U.S.DOE and PNC of Japan, using the ZPPR facility at ANL-Idaho in 1978 to 1979. The JUPITER-I experiment was a series of critical experiments for conventional two-zone homogeneous cores of 600 to 800 MWe-class LMFBR, including seven experimental cores The nuclear characteristics recorded here include criticality, control rod reactivity, reaction rate distribution, sodium void reactivity, sample reactivity, Doppler reactivity, gamma heating and neutron spectrum. (1)ZPPR-9 : two-region cylindrical clean core with volume of app. 4,600 liters, (2)ZPPR-10A : hexagonal engineering-mockup core with 19 cotrol-rod positions(CRPs), (3)ZPPR-10B : changes seven CRPs to control rods(CRs) from ZPPR-10A, (4)ZPPR-10C : volume of app. 6,200 liters with similar core arrangement to ZPPR-10A, (5)ZPPR-10D : 31 CRPs with the same volume as ZPPR-10C, (6)ZPPR-10D/1 : changes the central CRP to a CR from ZPPR-10D, and, (7)ZPPR-10D/2 : changes seven CRPs to CRs from ZPPR-10D. The present work is a part of efforts to develop a standard data base for LMFBR core nuclear design at PNC. The detail of experimental data is thoroughly recorded here so as to re-analyze these experiments in future. In addition, these experimental data are installed in the computer system at OEC for convenience of analytical code input.
Murakami, Hiroyuki*; Kanamori, Masashi; Nakamoto, Athushi*; Seki, Akio
PNC TN841 81-57, 19 Pages, 1981/10
no abstracts in English
