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JAEA Reports

Conceptual study of transmutation experimental facility, 2; Study on ADS target test facility

Sasa, Toshinobu; Umeno, Makoto*; Mizubayashi, Hiroshi*; Mori, Keijiro*; Futakawa, Masatoshi; Saito, Shigeru; Kai, Tetsuya; Nakai, Kimikazu*; Zako, Akira*; Kasahara, Yoshiyuki*; et al.

JAERI-Tech 2005-021, 114 Pages, 2005/03

JAERI-Tech-2005-021.pdf:9.66MB

To perform the research and development for accelerator-driven system (ADS), Japan Atomic Energy Research Institute (JAERI) plans to build a Transmutation Experimental Facility under the JAERI-KEK joint J-PARC program. Transmutation Experimental Facility consists of two buildings, Transmutation Physics Experimental Facility to make reactor physics experiment with subcritical core, and ADS Target Test Facility for the preparation of irradiation database for various structural materials. In this report, purpose to build, experimental schedule, and design study of the ADS target test facility with drawer type spallation target are summarized.

Journal Articles

Shielding design of the 200kW Pb-Bi spallation target for the transmutation experimental facility

Sasa, Toshinobu; Oigawa, Hiroyuki; Tayama, Ryuichi*; Hayashi, Katsumi*

Journal of Nuclear Science and Technology, 41(Suppl.4), p.30 - 33, 2004/03

The construction of Transmutation Experimental Facility (TEF) is planned under the framework of Japan Proton Accelerator Research Complex (J-PARC) project. A liquid lead-bismuth (Pb-Bi) spallation target with beam power of 600MeV-200kW will be installed into the TEF. Analyses were performed to determine the effective thickness of biological shield for Pb-Bi target by using both MCNPX and ATRAS code system. Thickness of around 6m should be required to decrease the radiation level. The streaming analyses through the proton injection beam duct and the primary cooling circuit piping were also performed. The result of the beam duct streaming shows good agreement between the results of MCNPX and DUCT-III. The additional shield must be installed to suppress the activation of accelerator components. In the case of streaming through the primary cooling circuit piping, it is proved that the radiation level at the exit of the shield is allowable. The radiation level can be much more reduced by optimizing the bending position and length of the piping.

Journal Articles

Benchmark analyses of neutron streaming experiments for proton accelerator facilities

Nakano, Hideo*; Masukawa, Fumihiro; Nakashima, Hiroshi; Sasamoto, Nobuo*; Tayama, Ryuichi*; Handa, Hiroyuki*; Hayashi, Katsumi*

Journal of Nuclear Science and Technology, 41(Suppl.4), p.50 - 53, 2004/03

In order to estimate accuracy of the various calculation methods for the neutron streaming through a maze and duct in proton accelerator facilities, we performed benchmark analyses by using the radiation shielding design codes. According to the results of the benchmark analyses, it is concluded that NMTC/MCNP, MCNPX and DUCT-III are applicable to actual calculation of the duct-streaming radiations for J-PARC.

Journal Articles

Analyses of streamed neutron spectra at TIARA using DUCT-III

Masukawa, Fumihiro; Nakano, Hideo*; Nakashima, Hiroshi; Sasamoto, Nobuo; Tayama, Ryuichi*; Hayashi, Katsumi*; Shin, Kazuo*

Journal of Nuclear Science and Technology, 41(Suppl.4), p.46 - 49, 2004/03

A simple design code for duct-streaming radiations, DUCT-III was applied to the analyses of the streamed neutron spectra measured at TIARA labyrinth with two bends. The code satisfactorily reproduced the measured neutron energy spectra and the Monte Carlo calculations, except that every calculation overestimated the measured thermal components by factor of 2 or 3.

JAEA Reports

Verification of the DUCT-III for calculation of high energy neutron streaming

Masukawa, Fumihiro; Nakano, Hideo*; Nakashima, Hiroshi; Sasamoto, Nobuo; Tayama, Ryuichi*; Handa, Hiroyuki*; Hayashi, Katsumi*; Hirayama, Hideo*; Shin, Kazuo*

JAERI-Tech 2003-018, 42 Pages, 2003/03

JAERI-Tech-2003-018.pdf:1.7MB

no abstracts in English

Journal Articles

Analyses of high energy neutron streaming experiments using DUCT-III

Masukawa, Fumihiro; Nakashima, Hiroshi; Sasamoto, Nobuo; Nakano, Hideo*; Tayama, Ryuichi*

Journal of Nuclear Science and Technology, 39(Suppl.2), p.1268 - 1271, 2002/08

no abstracts in English

JAEA Reports

Verification of corrosion product behavior analysis code for prediction for JOYO MK-II and Monju reactors

*; *; *

PNC TJ902 85-06, 549 Pages, 1985/06

PNC-TJ902-85-06.pdf:11.47MB

An analysis of the corrosion product behavior in the coolant system of the experimental fast breeder reactor JOYO was performed in order to verify an accuracy of the corrosion product behavior analysis code PSYCHE, and to confirm an applicability of parameters obtained from the in-loop-experiments. The PSYCHE code was also applied to predict the corrosion product behavior in scheduled JOYO operation condition and in scheculed MONJU, the prototype fast breeder reactor, operation condition. The PSYCHE code is based on a solution-precipitation model and the verification was performed by comparing the CP deposition density and dose rate of the primary sodium pipings between calculation and measurement. The comparison leads to the results that calculated deposition density agrees with the measurement within factors of 0.5 to 1.2 for $$^{54}$$Mn and within factors of 0.4 to 2.1 for $$^{60}$$Co, and that the calculated dose rates agree with the measurement within an error of 20-30%. The primary results derived from the analysis of the JOYO MK-II up to the 17-th full power cycle (Apr. '88) are that the released CP inventory would be gradually increased and be about 3.6 times higher for $$^{54}$$Mn and about 5.0 times higher for $$^{60}$$Co than those at the 4-th annual inspection (Jan. '84) and, according to this release increasement, dose rates around the primary pipings would reach 100 to 200 mR/h and at the maximum reach 400 mR/h at the nozzle of the IHX. From the analysis of MONJU up to the 57-th full power cycle, it is expected that the release inventory is about 780Ci for $$^{54}$$Mn, 470Ci for $$^{58}$$Co, 140Ci for $$^{51}$$Cr and 50Ci for $$^{60}$$Co at 10 days after reactor shutdown. Dose rates in the primary heat transport system vault are expected to reach about 1100 mR/h at the nozzle of the IHX and about 50 mR/h at a point 2m from the primary piping. It is predicted that $$^{54}$$Mn, $$^{58}$$Co and $$^{51}$$Cr behavior is determined during the first 5 cycles and ...

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