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Journal Articles

Measurement of displacement cross-section for structural materials in High-Power Proton Accelerator Facility

Meigo, Shinichiro; Matsuda, Hiroki; Iwamoto, Yosuke; Iwamoto, Hiroki; Hasegawa, Shoichi; Maekawa, Fujio; Yoshida, Makoto*; Ishida, Taku*; Makimura, Shunsuke*; Nakamoto, Tatsushi*

Proceedings of 9th International Particle Accelerator Conference (IPAC '18) (Internet), p.499 - 501, 2018/06

no abstracts in English

Journal Articles

New remarks on KERMA factors and DPA cross section data in ACE files

Konno, Chikara; Sato, Satoshi; Ota, Masayuki; Kwon, Saerom; Ochiai, Kentaro

Fusion Engineering and Design, 109-111(Part.B), p.1649 - 1652, 2016/11

Recently we have examined KERMA factors and DPA cross section data in the latest official ACE files of JENDL-4.0, ENDF/B-VII.1, JEFF-3.2 and FENDL-3.0 in more detail and we found out the following new problems on the KERMA factors and DPA cross section data. (1) NJOY bugs and incorrect nuclear data generated KERMA factors and DPA cross section data of no increase with decreasing neutron energy in low neutron energy. (2) Huge helium production data caused drastically large KERMA factors and DPA cross section data in low neutron energy. (3) It seemed that NJOY could not adequately process capture cross section data in File 6, not File 12-15. (4) KERMA factors with the kinematics method are not correct for nuclear data libraries without detailed secondary particle data (energy-angular distribution data). These problems should be resolved based on our study.

Journal Articles

Primary radiation damage in materials

Nordlund, K.*; Sand, A. E.*; Granberg, F.*; Zinkle, S. J.*; Stoller, R.*; Averback, R. S.*; Suzudo, Tomoaki; Malerba, L.*; Banhart, F.*; Weber, W. J.*; et al.

NEA/NSC/DOC(2015)9 (Internet), 86 Pages, 2015/00

Within this report, we review the current understanding of primary radiation damage from neutrons, ions and electrons with emphasis on the range of validity of the dpa concept in all main classes of materials, and in particular discuss known shortcomings. We recognise that the current NRT-dpa standard is fully valid in the sense of a scaled radiation exposure measure, as it is essentially proportional to the radiation energy deposited per volume. As such, it is highly recommended to be used in reporting neutron damage results to enable comparison between different nuclear reactor environments and ion irradiations. However, in the sense of a measure of damage production the NRT-dpa value has several well-known problems. We discuss this matter and propose an improved dpa definition.

JAEA Reports

Research and development on partitioning in JAERI; Review of the research activities until the development of 4-group partitioning process

Morita, Yasuji; Kubota, Masumitsu*

JAERI-Review 2005-041, 35 Pages, 2005/09

JAERI-Review-2005-041.pdf:2.24MB

Research and development on Partitioning in JAERI are reviewed in the present report from the beginning to the development of the 4-Group Partitioning Process and its test with real high-level liquid waste (HLLW). In the 3-Group Partitioning Process established in around 1980, elements in HLLW are separated into 3 groups of transuranium element group, Sr-Cs group and the other element group. The 4-Group Partitioning Process subsequently developed contains the separation of Tc-platinum group metals additionally. The process was tested to demonstrate its performance with real concentrated HLLW. Until then, various separation methods for various elements were studied and selection and optimization of the separation methods were carried out to establish the process. Review of the experience, findings and results is very important and valuable for future study on partitioning. The present report is prepared from this point of view.

Journal Articles

DPA Calculation in Japanese Spallation Neutron Source

Harada, Masahide; Watanabe, Noboru; Konno, Chikara; Meigo, Shinichiro; Ikeda, Yujiro; Niita, Koji*

Journal of Nuclear Materials, 343(1-3), p.197 - 204, 2005/06

 Times Cited Count:21 Percentile:14.34(Materials Science, Multidisciplinary)

For a construction of maintenance and storage scenarios for JSNS, lives of structure material need to be estimated. DPA (Displacement per Atom) was a major index of radiation damage. So we evaluated DPA value of each component. Function of the DPA calculation was equipped to the PHITS code, which was particle and heavy ion transport code. For DPA calculation, displacement cross section was necessary. Displacement cross sections of neutron below 150 MeV were processed by the NJOY code from LA150 library and those of neutron above 150MeV and proton in the all energy region were obtained from energies of fragments calculated in the PHITS. By using the PHITS, we calculated DPA values and DPA mapping. We obtained that the peak DPA values at end of 5000MWh operation were 4.1 for target vessel, 2.8 for reflector and moderator vessels, and 0.4 for proton beam windows, respectively. We estimated the target life at 1 year and the moderator life at 6 year.

Journal Articles

Synergistic effect of displacement damage and helium atoms on radiation hardening of F82H at TIARA facility

Ando, Masami; Wakai, Eiichi; Sawai, Tomotsugu; Tanigawa, Hiroyasu; Furuya, Kazuyuki; Jitsukawa, Shiro; Takeuchi, Hiroshi; Oka, Keiichiro*; Onuki, Somei*; Koyama, Akira*

Journal of Nuclear Materials, 329-333(2), p.1137 - 1141, 2004/08

 Times Cited Count:37 Percentile:6.99(Materials Science, Multidisciplinary)

One of the most crucial issues on R&D of reduced activation ferritic/martensitic steels is the effect of helium on the degradation of fracture toughness. The synergistic effects of displacement damage and helium on F82H steel can be partially simulated by martensitic steels doped with $$^{10}$$B or $$^{58}$$Ni in a mixed spectrum fission reactor. However, the control of helium production rate is difficult and the chemical effects of B or Ni doping on mechanical property are not small. Therefore, multi-ion irradiation method is the most convenient and accurate method to simulate various irradiation conditions. Moreover, the effects of helium on irradiation hardening behavior can be examined by combining ion-irradiation with ultra micro-indentation technique. The purpose of this study is to examine the extra component of radiation hardening due to implanted helium in F82H. The extra component of irradiation hardening due to helium was hardly detected in the dual-beam irradiation. Therefore, the effect on irradiation hardening below 630K of helium ($$<$$500 appm) was very small.

Journal Articles

Triple ion beam irradiation tests on window materials of spallation targets

Futakawa, Masatoshi; Kurata, Yuji; Henry, J.*; Ioka, Ikuo; Saito, Shigeru; Naito, Akira

FZKA-6876, p.166 - 171, 2003/12

A report at MEGAPIE(Megawatt Pilot Experiment) Technical R & D Meeting is collected into an FZK report. Triple ion beam irradiation tests on T91 specimens were conducted under MEGAPIE condition using TIARA facility at JAERI. Results of triple ion beam irradiation up to 15dpa, 1400appm He, 10000appm H at 320$$^{circ}$$C were compared with those of single or dual beam irradiation of Fe or He ions by use of a micro-indentation method. Hardsness increase was mainly attributed to displacement damage by Fe ions. A little effect on hardness was found on simultaneous implantation of He and H ions. An analysis method to predict mechanical characterization form micro-indentation test results was developed on ion irradiated materials.

JAEA Reports

Studies on actinide separation process from high-level liquid waste (Joint research)

Morita, Yasuji; Tachimori, Shoichi; Koma, Yoshikazu*; Aoshima, Atsushi*

JAERI-Research 2002-017, 20 Pages, 2002/08

JAERI-Research-2002-017.pdf:1.32MB

The present report describes the results of a joint study between Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Energy Research Institute (JAERI) on actinide separation process from high-level liquid waste. The purpose of the joint study is to point out common subjects in process development by an overall evaluation of each actinide separation process: TRUEX/SETFICS Process studied in JNC and DIDPA Extraction Process studied in JAERI. The result of the evaluation showed that both processes have common subjects to be studied in sub-processes such as treatment step for spent solvent or DTPA waste solution and solvent washing step for recycling, although the main process is different from each other. It is necessary to develop the sub-processes and to test the whole process including the sub-processes. Two essential requirements: the cost reduction and the minimization of secondary wastes, are very important in future research and development for more rational and effective actinide separation process.

Journal Articles

Back-extraction of tri- and tetravalent actinides from diisodecylphosphoric acid (DIDPA) with hydrazine carbonate

Watanabe, Masayuki; Tatsugae, Ryozo*; Morita, Yasuji; Kubota, Masumitsu*

Journal of Radioanalytical and Nuclear Chemistry, 252(1), p.53 - 57, 2002/04

 Times Cited Count:5 Percentile:61.28(Chemistry, Analytical)

no abstracts in English

JAEA Reports

Transport analysis of tungsten impurity in ITER-FEAT

Murakami, Yoshiki*; Amano, Tsuneo*; Shimizu, Katsuhiro; Shimada, Michiya; Ogawa, Yuichi*

JAERI-Research 2001-049, 58 Pages, 2001/11

JAERI-Research-2001-049.pdf:3.11MB

no abstracts in English

Journal Articles

Back-extraction of uranium(VI) from organophosphoric acid with hydrazine carbonate

Watanabe, Masayuki; Tatsugae, Ryozo*; Shirahashi, Koichi; Morita, Yasuji; Kubota, Masumitsu*

Journal of Radioanalytical and Nuclear Chemistry, 250(2), p.377 - 379, 2001/11

 Times Cited Count:3 Percentile:69.87(Chemistry, Analytical)

no abstracts in English

JAEA Reports

Evaluation of neutronic irradiation field of improved LEU-core in the JMTR; Comparison of neutron flux and neutron spectrum with previous LEU-core

Nagao, Yoshiharu; Takemoto, Noriyuki; Takeda, Takashi

JAERI-Tech 2001-069, 83 Pages, 2001/10

JAERI-Tech-2001-069.pdf:4.76MB

no abstracts in English

Journal Articles

JAERI/KEK target material program overview

Kikuchi, Kenji; Kogawa, Hiroyuki; Sasa, Toshinobu

JAERI-Conf 2001-002, p.1251 - 1258, 2001/03

no abstracts in English

Journal Articles

Characterization of neutron field for stainless steel irradiation experiments in JMTR

Shimakawa, Satoshi; Nagao, Yoshiharu; Fujiki, Kazuo

Reactor Dosimetry: Radiation Metrology and Assessment (ASTM STP 1398), p.244 - 251, 2001/00

no abstracts in English

Journal Articles

JENDL PKA/KERMA file for IFMIF project

Fukahori, Tokio; Chiba, Satoshi; Shibata, Keiichi; Ikeda, Yujiro; Aruga, Takeo; Watanabe, Yukinobu*; Murata, Toru*; Yamano, Naoki*; Kawai, Masayoshi*

Reactor Dosimetry: Radiation Metrology and Assessment (ASTM STP 1398), p.591 - 598, 2001/00

no abstracts in English

Journal Articles

In-pile and post-irradiation creep of type 304 stainless steel under different neutron spectra

Kurata, Yuji; Itabashi, Yukio; Mimura, Hideaki*; Kikuchi, Taiji; Amezawa, Hiroo; Shimakawa, Satoshi; Tsuji, Hirokazu; Shindo, Masami

Journal of Nuclear Materials, 283-287(Part.1), p.386 - 390, 2000/12

 Times Cited Count:4 Percentile:64.02

no abstracts in English

Journal Articles

Compression properties of neutron irradiated beryllium pebbles

Ishitsuka, Etsuo; Kawamura, Hiroshi; Terai, Takayuki*; Tanaka, Satoru*

Fusion Engineering and Design, 51-52, p.123 - 126, 2000/11

 Times Cited Count:1 Percentile:86.42

no abstracts in English

JAEA Reports

Cold and semi-hot tests of 4-group partitioning process at NUCEF

Morita, Yasuji; Yamaguchi, Isoo; Fujiwara, Takeshi; Mizoguchi, Kenichi*; Kubota, Masumitsu*

JAERI-Research 2000-024, 55 Pages, 2000/06

JAERI-Research-2000-024.pdf:2.24MB

no abstracts in English

JAEA Reports

Evaluation of neutronic characteristic of irradiation field in MEU6-core; Comparison of neutron flux and neutron spectrum in MEU6-core and mixed-core

Nagao, Yoshiharu; Komukai, Bunsaku; Tabata, Toshio; Takeda, Takashi; Fujiki, Kazuo

JAERI-Tech 99-063, 57 Pages, 1999/08

JAERI-Tech-99-063.pdf:2.78MB

no abstracts in English

JAEA Reports

Development of partitioning process; Back-extraction of actinoid and lanthanoid with hydrazine carbonate

Watanabe, Masayuki; Tatsugae, Ryozo*; *; Morita, Yasuji; Kubota, Masumitsu

JAERI-Research 99-034, 55 Pages, 1999/05

JAERI-Research-99-034.pdf:1.7MB

no abstracts in English

57 (Records 1-20 displayed on this page)