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Journal Articles

Uncertainty reduction of sodium void reactivity using data from a sodium shielding experiment

Maruyama, Shuhei; Endo, Tomohiro*; Yamamoto, Akio*

Journal of Nuclear Science and Technology, 61(1), p.31 - 43, 2024/01

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

This study investigated the feasibility of reducing the uncertainty associated with fast-reactor-core design by sharing an experimental database between different fields (e.g., reactor physics and radiation shielding) using data assimilation techniques. As the first step in this study, we focused on the ORNL sodium shielding experiment and investigated the possibility of using the experimental data to reduce the uncertainty in sodium void reactivity (SVR), which is the most important safety parameter for sodium-cooled fast reactors. A sensitivity analysis based on the Generalized Perturbation Theory was performed for the sodium shielding experiment. Using the sensitivity coefficients evaluated here and those of the sodium void reactivity previously evaluated by the JAEA, we showed that sodium shielding experimental data can contribute to the uncertainty reduction of SVR by adopting the cross-section adjustment method. Based on this study, the uncertainty reduction effect is expected to be significant, especially for SVR dominated by neutron-leakage phenomena. Although new reactor physics experimental data on SVR may be difficult to obtain, the results of this study suggest that data from sodium shielding experiments can partially substitute for this role. This study demonstrated the value of the mutual use of integral experimental data in fast reactor designs.

Journal Articles

JENDL-5 benchmark test for shielding applications

Konno, Chikara; Ota, Masayuki*; Kwon, Saerom*; Onishi, Seiki*; Yamano, Naoki*; Sato, Satoshi*

Journal of Nuclear Science and Technology, 60(9), p.1046 - 1069, 2023/09

 Times Cited Count:4 Percentile:98.08(Nuclear Science & Technology)

JENDL-5 was validated from a viewpoint of shielding applications under the Shielding Integral Test Working Group of the JENDL Committee. The following benchmark experiments were selected: JAEA/FNS in-situ experiments, Osaka Univ./OKTAVIAN TOF experiments, ORNL/JASPER sodium experiments, NIST iron experiment and QST/TIARA experiments. These experiments were analyzed with MCNP and nuclear data libraries (JENDL-5, JENDL-4.0 or JENDL-4.0/HE, ENDF/B-VIII.0 and JEFF-3.3). The analysis results demonstrate that JENDL-5 is comparable to or better than JENDL-4.0 or JENDL-4.0/HE, ENDF/B-VIII.0 and JEFF-3.3.

Journal Articles

Proposal on how to proceed with Verification and Validation of radiation shielding analyses

Okumura, Keisuke; Sakamoto, Yukio*; Tsukiyama, Toshihisa*

Shahei Kaiseki No V&V Gaidorain Sakutei Ni Mukete, p.4 - 8, 2023/03

no abstracts in English

Journal Articles

Implementation of resonance upscattering treatment in FRENDY nuclear data processing system

Yamamoto, Akio*; Endo, Tomohiro*; Chiba, Go*; Tada, Kenichi

Nuclear Science and Engineering, 196(11), p.1267 - 1279, 2022/11

 Times Cited Count:1 Percentile:31.61(Nuclear Science & Technology)

The resonance upscattering effect (the thermal agitation effect) is incorporated in the generation capability of multi-group neutron cross sections of the FRENDY nuclear data processing system. The resonance upscattering effect is considered by (1) the variation of self-shielding factors (effective cross sections) due to the change in ultra-fine group spectrum and (2) the variation of group-to-group elastic scattering cross sections. In the verification calculations, impacts on the ultra-fine group spectrum, effective cross sections, and neutronics characteristics (the Doppler effect) are confirmed. The effect of energy group structure and the treatments of resonance upscattering on the Doppler effect through the variation of effective cross sections and the elastic scattering matrix are studied. The results indicate that the FRENDY can provide appropriate multi-group cross sections considering the resonance upscattering effect.

JAEA Reports

Radiation shielding analysis of the upper structure of an accelerator-driven system

Iwamoto, Hiroki; Meigo, Shinichiro; Nakano, Keita; Yee-Rendon, B.; Katano, Ryota; Sugawara, Takanori; Nishihara, Kenji; Sasa, Toshinobu; Maekawa, Fujio

JAEA-Research 2021-012, 58 Pages, 2022/01

JAEA-Research-2021-012.pdf:7.23MB

A radiation shielding analysis was performed for the structure located above the spallation target of an accelerator-driven system (ADS), assuming one cycle of an 800 MW thermal and 30 MW beam power operation. In this analysis, the Monte Carlo particle transport code PHITS and the activation analysis code DCHAIN-PHITS were used. The structures to be analyzed are a beam duct above the target, a beam transport room located above the ADS reactor vessel, beam transport equipment, and the room ceiling. For each structure, the radiation doses and radioactivities during and after the operation were estimated. Furthermore, the shielding structure of the ceiling was determined. As a result, it was found that the radiation dose at the site boundary would be sufficiently lower than the legal limit by applying the determined shielding structure. Moreover, under the condition of this study, it was shown that the effective dose rate around the beam transport equipment positioned above the target after the operation exceeded 10 mSv/h, and that the maintenance and replacement of the equipment in the room would require remote handling.

Journal Articles

Adaptive setting of background cross sections for generation of effective multi-group cross sections in FRENDY nuclear data processing code

Yamamoto, Akio*; Endo, Tomohiro*; Tada, Kenichi

Journal of Nuclear Science and Technology, 58(12), p.1343 - 1350, 2021/12

 Times Cited Count:1 Percentile:16.35(Nuclear Science & Technology)

An adaptive setting method of background cross sections is implemented to FRENDY/MG, which is a multi-group neutron cross section generation code. In the present adaptive setting method, the range of background cross section is initially divided into 10 equal intervals and unnecessary background cross section points, at which self-shielding factors or reaction rates can be accurately interpolated, are eliminated. If the interpolation accuracy in an interval is not sufficient, the interval is successively halved until sufficient interpolation accuracy is obtained. For accurate interpolation of self-shielding factor or reaction rates, the monotone cubic interpolation is used. Verification calculations are carried out for all isotopes in JENDL-4.0 and -4.0u. Calculation results indicate that typical numbers of background cross sections are from 10 to 25 when the monotone cubic interpolation and error tolerance of 0.01 for self-shielding factors are used.

Journal Articles

Radiological estimation and validation for the Accelerator-Based Boron Neutron Capture Therapy Facility at the Ibaraki Neutron Medical Research Center

Nakashima, Hiroshi; Nakamura, Takemi; Kobayashi, Hitoshi*; Tanaka, Susumu*; Kumada, Hiroaki*

NEA/NSC/R(2021)2 (Internet), p.142 - 151, 2021/12

Aiming of development of facilities for boron neutron capture therapy (BNCT) that can be installed in hospitals, an accelerator-based BNCT facility is being developed at the Ibaraki Neutron Medical Research Center under a collaboration among the Japan Atomic Energy Agency, the High Energy Accelerator Research Organization, the University of Tsukuba, and other institutions. It consists of a proton accelerator, having a maximum beam power of 80 kW, and a target, moderator, collimator and shield (TMCS) system. For the design concept, to satisfy the BNCT beam conditions and achieve a low activation, the radiation behavior in the TMCS system was simulated by the Monte Carlo method and this system configuration was optimized accordingly. In addition, the radiation estimation of the TMCS system was verified via several experiments and its applicability for BNCT was proved. This report reviews the estimation and validation studies for the development of the accelerator-based BNCT facility.

Journal Articles

Self-shielding effect of double heterogeneity for plutonium burner HTGR design

Fukaya, Yuji; Goto, Minoru; Ohashi, Hirofumi

Annals of Nuclear Energy, 138, p.107182_1 - 107182_9, 2020/04

AA2019-0041.pdf:0.93MB

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

The investigation on self-shielding effect of double heterogeneity for plutonium burner High Temperature Gas-cooled Reactor (HTGR) design has been performed. Plutonium burner HTGR designed in the previous study by using the advantage of double heterogeneity to control excess reactivity. In the present study, the mechanism of the self-shielding effect is elucidated by the analysis of burn-up calculation and reactivity decomposition based on exact perturbation theory. As a result, it is revealed that the characteristics of burn-up reactivity are determined by resonance cross section peak at 1 eV of $$^{240}$$Pu due to the surface term of background cross section, this is, the characteristics of neutron leakage from fuel lump and collision to a moderator. Moreover, significant spectrum shift is caused during the burn-up period, and it enhances reactivity worth of $$^{239}$$Pu and $$^{240}$$Pu in EOL.

Journal Articles

Activation in injection area of J-PARC 3-GeV rapid cycling synchrotron and its countermeasures

Yamamoto, Kazami; Yamakawa, Emi*; Takayanagi, Tomohiro; Miki, Nobuharu*; Kamiya, Junichiro; Saha, P. K.; Yoshimoto, Masahiro; Yanagibashi, Toru*; Horino, Koki*; Nakanoya, Takamitsu; et al.

ANS RPSD 2018; 20th Topical Meeting of the Radiation Protection and Shielding Division of ANS (CD-ROM), 9 Pages, 2018/08

The existing beam power of the J-PARC Rapid Cycling Synchrotron is up to 500 kW, and higher radiation doses are concentrated in the injection area. These activations are caused by the interaction between the foil and the beam. To reduce dose exposure to workers near the injection point, we study a new design of the injection scheme. Experience has shown that eddy currents are generated in the metal flange near the magnet owing to the pulsed magnetic field, and the temperature exceeds 100 degrees C. The shield installed in the new injection system needs to have a layer structure, in which an insulator is inserted between iron shields to reduce the eddy current. From the results of the shielding calculation, even if 1 mm of polyethylene was inserted between two 9-mm-thick SUS 316 plates, which serve as shielding material, the shielding performance was reduced only about 5%, and we confirmed that it would function well.

Journal Articles

Review of $$gamma$$-ray exposure buildup factors

Matsuda, Norihiro; Onishi, Seiki*; Sakamoto, Yukio*; Nobuhara, Fumiyoshi*

Heisei 29-Nendo Kani Shahei Kaiseki Kodo Rebyu Wakingu Gurupu Katsudo Hokokusho (Internet), p.20 - 28, 2018/08

no abstracts in English

Journal Articles

Shielding effect on secondary cosmic-ray neutron- and muon-induced soft errors

Abe, Shinichiro; Sato, Tatsuhiko

Proceedings of Radiation Effects on Components and Systems Conference 2016 (RADECS 2016) (Internet), 5 Pages, 2016/00

Secondary cosmic-ray neutron have been recognized as a major cause of soft error for microelectronics on ground. Recently, the effect of secondary cosmic-ray muon on soft error is concerned as semiconductor devices become sensitive to radiation. In this study, we investigate the shielding effect on secondary cosmic-ray neutron- and muon-induced SER. Transports of secondary cosmic-ray neutrons and muons in a building are simulated by PHITS with considering distributions of energy and zenith-angle of secondary cosmic-rays by PARMA 4.0 which is the analytical model for estimating cosmic-ray fluxes nearly anytime and anywhere in the world. The calculated neutron fluxes are in surprisingly good agreement with measured data. The soft errors in 25-nm bulk-design NMOSFET caused by neutrons and muons in the open air and on the first floor of the building are analyzed based on the MSV model using PHITS. It is found that the shielding effect of the building only contributes to decrease neutron-induced SER. As a result, muon-induced SER is about 20% of that caused by neutron on the first floor. Therefore it is necessary to consider the secondary cosmic-ray muon-induced SER when reliability of devices used in the building is evaluated.

Journal Articles

Activation, Radiation shielding materials

Sukegawa, Atsuhiko; Iida, Hiromasa*; Itoga, Toshio*; Okumura, Keisuke; Kai, Tetsuya; Konno, Chikara; Nakashima, Hiroshi; Nakamura, Takashi*; Ban, Shuichi*; Yashima, Hiroshi*; et al.

Hoshasen Shahei Handobukku; Kisohen, p.299 - 356, 2015/03

no abstracts in English

Journal Articles

Homogeneity tests on neutron shield concrete

Okuno, Koichi*; Iikura, Hiroshi

Nuclear Science and Techniques, 25(S1), p.S010604_1 - S010604_5, 2014/12

no abstracts in English

Journal Articles

Education method on Monte Carlo Analysis in atomic energy

Sakurai, Kiyoshi; Yamamoto, Toshihiro

Nihon Genshiryoku Gakkai Wabun Rombunshi, 4(4), p.248 - 258, 2005/12

no abstracts in English

Journal Articles

Experiment and analyses for 14 MeV neutron streaming through a dogleg duct

Yamauchi, Michinori*; Ochiai, Kentaro; Morimoto, Yuichi*; Wada, Masayuki*; Sato, Satoshi; Nishitani, Takeo

Radiation Protection Dosimetry, 116(1-4), p.542 - 546, 2005/12

 Times Cited Count:3 Percentile:24.22(Environmental Sciences)

no abstracts in English

Journal Articles

Shielding design of the ITER NBI Duct for nuclear and bremsstrahlung radiation

Sato, Satoshi; Iida, Hiromasa; Yamauchi, Michinori*; Nishitani, Takeo

Radiation Protection Dosimetry, 116(1-4), p.28 - 31, 2005/12

 Times Cited Count:3 Percentile:24.22(Environmental Sciences)

no abstracts in English

Journal Articles

Nuclear "pasta" structures and the charge screening effect

Maruyama, Toshiki; Tatsumi, Toshitaka*; Voskresensky, D. N.*; Tanigawa, Tomonori; Chiba, Satoshi

Physical Review C, 72(1), p.015802_1 - 015802_11, 2005/07

 Times Cited Count:167 Percentile:99.09(Physics, Nuclear)

no abstracts in English

JAEA Reports

Shielding design for target trolley for a spallation neutron source in the J-PARC project

Tamura, Masaya; Maekawa, Fujio; Harada, Masahide; Haga, Katsuhiro; Konno, Chikara

JAERI-Tech 2005-020, 58 Pages, 2005/03

JAERI-Tech-2005-020.pdf:18.82MB

no abstracts in English

Journal Articles

Structured mixed phase at charged kaon condensation

Maruyama, Toshiki; Tatsumi, Toshitaka*; Voskresensky, D. N.*; Tanigawa, Tomonori; Chiba, Satoshi

Nuclear Physics A, 749, p.186c - 189c, 2005/03

no abstracts in English

Journal Articles

Radiation safety design study of J-PARC (Japan Proton Accelerator Research Complex)

Nakashima, Hiroshi; Safety Group of J-PARC

Monte Karuro Keisanho Kodoka No Genjo; Dai-3-Kai Monte Karuro Shimyureshon Kenkyukai Hobunshu, p.75 - 83, 2004/12

Design policy for radiation safety issues, design criteria, calculation conditions for shielding design, method for design and safety estimation and the present status of shielding design are reported in Japan Proton Accelerator Research Complex.

270 (Records 1-20 displayed on this page)