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Sakanaka, Shogo*; Akemoto, Mitsuo*; Aoto, Tomohiro*; Arakawa, Dai*; Asaoka, Seiji*; Enomoto, Atsushi*; Fukuda, Shigeki*; Furukawa, Kazuro*; Furuya, Takaaki*; Haga, Kaiichi*; et al.
Proceedings of 1st International Particle Accelerator Conference (IPAC '10) (Internet), p.2338 - 2340, 2010/05
Future synchrotron light source using a 5-GeV energy recovery linac (ERL) is under proposal by our Japanese collaboration team, and we are conducting R&D efforts for that. We are developing high-brightness DC photocathode guns, two types of cryomodules for both injector and main superconducting (SC) linacs, and 1.3 GHz high CW-power RF sources. We are also constructing the Compact ERL (cERL) for demonstrating the recirculation of low-emittance, high-current beams using above-mentioned critical technologies.
Hanaki, Hiroshi*; Sanda, Toshio*; Ohashi, Masahisa*
JAEA-Review 2008-047, 266 Pages, 2008/10
JAEA-Review-2008-047.pdf:62.06MB
It is thought to improve the prediction accuracy for burnup characteristics using many burnup data of "Joyo" effectively. It is thought the best way to adjust cross-sections using sensitivity coefficients of burnup characteristics to utilize burnup data of "Joyo". Therefore in this work computer codes for analyzing sensitivity coefficients of burnup characteristics had been prepared since 1992. The results are as follows: (1) The computer codes which could analyze sensitivity coefficients of burnup characteristics taking into consideration plural cycles and refueling were prepared, therefore it came to be able to adjust cross-sections using burnup data and to estimate the accuracy for design of large LMFBR cores. (2) The adequacy of prepared codes was made sure by comparing with direct calculations. (NB: This document is a translation of PNC TJ9124 94-007 Vol.2 published in March 1997.)
Sakanaka, Shogo*; Ago, Tomonori*; Enomoto, Atsushi*; Fukuda, Shigeki*; Furukawa, Kazuro*; Furuya, Takaaki*; Haga, Kaiichi*; Harada, Kentaro*; Hiramatsu, Shigenori*; Honda, Toru*; et al.
Proceedings of 11th European Particle Accelerator Conference (EPAC '08) (CD-ROM), p.205 - 207, 2008/06
Future synchrotron light sources based on the energy-recovery linacs (ERLs) are expected to be capable of producing super-brilliant and/or ultra-short pulses of synchrotron radiation. Our Japanese collaboration team is making efforts for realizing an ERL-based hard X-ray source. We report recent progress in our R&D efforts.
*; *; *
PNC TJ9124 97-003, 381 Pages, 1997/03
To develop nuclear design of LMFBR cores, they are important subjects of research and development to improve the accuracy in nuclear design of large LMFBR cores and to design highly efficient core more rationally. The adjusted nuclear cross-sections library had been made by being reflected the result of critical experiment of the JUPITER, etc. effectively as much as possible. And the distinct improvement of the accuracy in nuclear design of large LMFBR eores had been achieved. And the computer codes for analyzing sensitivity coefficients of burnup and temperature characteristics, adjusting cross-sections library and estimating the accuracy in nuclear design had been prepared to improve the prediction accuracy for burnup and temperature characteristics using many burnup and temperature data of "Joyo", etc. effectively. In the study, basic preparation of computer system had done by developing and improving the basic theoretical formula and confirming applicability of the system for large LMFBR. But, the system needed to be improved in the points of calculating model and efficiency of calculation to use for design work of the recycle reactor, Demonstration FBR, etc.. Therefore in this work, the total system for estimating the accuracy in nuclear design was prepared by improving present computer codes. The results are as follows: (1)The computer code to calculate sensitivity coefficients was made possible the three-dimensional calculation and relational system was improved. (2)The validity of the three-dimensional calculation was confirmed by comparing sensitivity coefficients which were calculated by three and two dimensional calculation model and by direct method. (3)The design to make usable system for estimating the accuracy was done by reviewing the whole of present system, for example, I/O data between computer codes, input method of geometric data, etc.. (4)The result of above investigation, unified program system using data base was adopted by ...
*; Sanda, Toshio*
PNC TJ9124 97-002, 178 Pages, 1997/03
To develop nuclear design of LMFBR cores, they are important subjects of research and development to improve the accuracy in nuclear design of large LMFBR cores and to design highly efficient core more rationally. The adjusted nuclear cross-sections library had been made by being reflected the result of critical experiment of the JUPITER, etc.effectively as much as possible. And the distinct improvement of the accuracy in nuclear design of large LMFBR cores had been achieved. But, this adjusted library published in 1991 should be improved utilizing the newest results of study for the stage in which nuclear design is required higher precision such as fundamental design of demonstration FBR, because it was adjusted by using the data of only JUPITER experiment, without burnup and temperature characteristics, basing on JENDL-2 published in early 1980s, and wasn't done the adjustment of inelastic scattering matrix. Therefore the object of this work is to make unified cross-section library that will be able to use for design stage from fundamental to approval by adjusting the newest domestic library, JENDL-3.2 published in 1994 and improving precision and trust in nuclear design. For the object, it will be used for adjustment that "Monju" and "Joyo" experimental data being owned by PNC, critical experimental data of ZPPR-2,3 and MOZART, burnup characteristics, and temperature characteristics. The results of this study are as follows: (1)It was prepared each C/E values, experimental and analysis errors, correlation factors, etc. of criticality, reaction rate ratio, control rod worth, and Doppler reactivity experimented in ZPPR-2,3. (2)It was prepared the data of C/E values, experimental and analysis errors, correlation factors, etc. of isothermal temperature coefficient experimented in SEFOR. (3)JENDL-3.2 library was preparatorily adjusted using the experimental data which had been already obtained. The effect of adjustment and validity of decided errors were ...
Ishido, Akio*; Hasegawa, Ken*; Hanaki, Tatsumi*; Ochiai, Yoji*; Shigeta, Naotaka*; Nagasaki, Yasushi*
JNC TN7400 2005-022, 224 Pages, 1996/04
JNC-TN7400-2005-022.PDF:9.36MB
None
*; *; Sanda, Toshio*
PNC TJ9124 96-007, 278 Pages, 1996/03
To develop nuclear design of LMFBR cores, they are important subjects of research and development to improve the accuracy in nuclear design of large LMFBR cores and to design highly efficient core more rationally. The adjusted nuclear cross-sections library had been made by being reflected the result of critical experiment of the JUPITER, etc.effectively as much as possible. And the distinctim provement of the accuracy in nuclear design of large LMFBR cores had been achieved. And the computer codes for analyzing sensitivity coefficients of burnup characteristics had been prepared to improve the prediction accuracy for burnup characteristics using many burnup data of "Joyo" effectively. As compared with critical experiment, Doppler reactivity is one of the great characteristics of LMFBR. Doppler reactivity is very important to assure core character of self-control and it is claimed to improve the prediction accuracy for it. But it is impossible to estimate the accuracy for present codes because it is much depend on self-shielding factor. Therefore in this work the system for estimating the accuracy in nuclear design of Doppler reactivity by improving present computer codes was studied. The results are as follows: (1)The method of analyzing sensitivity coefficients of Doppler reactivity was studied and computer codes was prepared by improving present codes. (2)Uncertainty of the gradient toward temperature of self-shielding factor of U238 capture reaction which is the most important reaction for Doppler reactivity was estimated preparatorily and formalized for using adjustment. (3)Uncertainties of experiment and analysis for Doppler reactivities in ZPPR-9 were arranged. (4)It was clarifled that it is possible to improve C/E values of Doppler reactivities without affecting other neutronic characteristics by doing preparatorily adjustment.
*; Sanda, Toshio*; *
PNC TJ9124 95-005, 467 Pages, 1995/03
To develop nuclear design of LMFBR cores, they are important subjects of research and development to improve the accuracy in nuclear design of large LMFBR cores and to design highly efficient core more rationally. The adjusted nuclear cross-sections library had been made by being reflected the result of critical experiment of the JUPITER, etc. effectively as much as possible. And the distinct improvement of the accuracy in nuclear design of large LMFBR cores had been achieved. And the computer codes for analyzing sensitivity coefficients of burnup characteristics had been prepared to improve the prediction accuracy for burnup characteristics using many burnup data of "Joyo" effectively. As compared with critical experiment, Doppler reactivity is one of the great characteristics of LMFBR. Doppler reactivity is very important to assure core character of self-control and it is claimed to improve the prediction accuracy for it. But it is impossible to estimate the accuracy for present codes because it is much depend on self-shielding factor. Therefore in this work the system for estimating the accuracy in nuclear design of Doppler reactivity by improving present computer codes was studied. The results are as follows: (1)The method of analyzing sensitivity coefficients of Doppler reactivity was studied and computer codes was prepared by improving present codes. (2)Uncertainty of the gradient toward temperature of self-shielding factor of U238 capture reaction which is the most important reaction for Doppler reactivity was estimated preparatorily and formalized for using adjustment. (3)Uncertainties of experiment and analysis for Doppler reactivities in ZPPR-9 were arranged. (4)It was clarified that it is possible to improve C/E values of Doppler reactivities without affecting other neutronic characteristics by doing preparatorily adjustment.
*; Sanda, Toshio*; *
PNC TJ9124 94-007, 723 Pages, 1994/03
PNC-TJ9124-94-007-Vol1.pdf:22.78MBPNC-TJ9124-94-007-Vol2.pdf:13.26MB
To develop nuclear design of LMFBR cores, they are important subjects of research and development to improve the accuracy in nuclear design of large LMFBR cores and to design highly efficient core more rationally. The adjusted nuclear cross-section library has beeen made by being reflected the result of critical experiment of the JUPITER, etc. effectively as much as possible. And the distinct improvement of the accuracy in nuclear design of large LMFBR cores has been achieved. In the design of large LMFBR cores, however, it is important to accurately estimate not only nuclear characteristics, for example, reaction rate distribution and control rod worth but also burnup characteristics, for example, burnup reactivity loss, breeding ratio and so on. Therefore, it is thought to improve the prediction accuracy for burnup characteristics using many burnup data of "JOYO" effectively. It is thought the best way to adjust cross-sections using sensitivity coefficients of burnup characteristics to utilize burnup data of "JOYO". It is able to know the accuracy quantitatively for burnup characteristics of large LMFBR by analyzing the sensitivity coefficients. Therefore in this work computer codes for analyzing sensitivity coefficients of burnup characteristics had been prepared since 1992. In 1992 cross-sections adjustment was done by using the data of "JOYO" and the effect was studied. In this year the adequacy of the codes was studied with a view of applying to design of large LMFBR cores. The results are as follows: (1)The computer codes which could analyze sensitivity coefficients of burnup characteristics taking into consideration plural cycles and refueling were prepared, therefore it came to be able to adjust cross-section using burnup data and to estimate the accuracy for design of large LMFBR cores. The characteristics are not only burnup reactivity loss, breeding ratio but also number density, criticality, reactivity worth, reaction rate ratio, and ....
Tsubota, Koji*; Ochiai, Yoji*; Hanaki, Tatsumi*; Hasegawa, Ken*; Okita, Masatoshi*; Koide, Kaoru*; Nagasaki, Yasushi*
JNC TN7400 2005-019, 114 Pages, 1993/04
JNC-TN7400-2005-019.PDF:7.46MB
None
*; *; Sanda, Toshio*
PNC TJ9124 93-009, 334 Pages, 1993/03
To commertialize LMFBR, they are important subjects of research and development to improve the accuracy in neutronic design of large LMFBR cores and to make be able to design highly efficient core more rationaoy. The adjusted library has been made by being reflected the result of critical experiment of the JUPITER, etc. effectively as much as possible by using the cross-sections adjustment method based on the probabilistic theory. And the distinct improvement of the accuracy in neutronic design of large LMFBR cores has been achieved. In the design of large LMFBR cores, however, it is important to accurately estimate not only neutronic characteristics, for example, reaction rate distribution and control rod worth but also burnup characteristics, for example, burnup reactivity loss, breeding ratio and so on. Therefore the objective of the work is to improve the prediction accuracy for burnup characteristics using many burnup data of "Joyo" effectively. For the objective computer codes for analyzing sensitivity coefficients of burnup characteristics were prepared and cross-sections adjustment using burnup data of "Joyo" was done and the effect for the improvement of the accuracy for burnup characteristics was estimated. The results are as follows: (1)The computer codes which could analyze sensitivity coefficients of burnup characteristics of LMFBR taking into consideration plural cycles and refueling were prepared and their adequacy was made sure by comparing with direct calculations. (2)It was clarified that it is possible to improve the accuracy of burnup characteristics without affecting statically neutronic characteristics so much by applying the burnup characteristics to cross-sections adjustment.
Hanaki, Shotaro; Mashimo, Ryutaro; Nanri, Tomohiro; Hayashi, Hirokazu
no journal, ,
The assessment of contamination distribution evaluates the type, radioactivity and distribution of radioactive materials remaining in the facility for the purpose of reducing the exposure of radiation workers and the surrounding public, formulating dismantling and removal methods and procedures, and evaluating the amount of radioactive waste generated during dismantling and removal work. In Monju, some structural materials around the reactor and primary sodium have been activated, and radioactive materials remain as secondary contamination on the inner surfaces of equipment and piping in the primary cooling system, although the total amount of radioactive materials is small. This presentation provides an overall overview of the assessment and the results of the assessment carried out in the first phase.
