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JAEA Reports

Development of module for TRU high temperature chemistry (Joint research)

Minato, Kazuo; Akabori, Mitsuo; Tsuboi, Takashi; Kurobane, Shiro; Hayashi, Hirokazu; Takano, Masahide; Otobe, Haruyoshi; Misumi, Masahiro*; Sakamoto, Takuya*; Kato, Isao*; et al.

JAERI-Tech 2005-059, 61 Pages, 2005/09

JAERI-Tech-2005-059.pdf:20.67MB

An experimental facility called the Module for TRU High Temperature Chemistry (TRU-HITEC) was installed in the Back-end Cycle Key Elements Research Facility (BECKY) of the Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF) for the basic studies of the behavior of the transuranium elements (TRU) in pyrochemical reprocessing and oxide fuels. TRU-HITEC consists of three alpha/gamma cells shielded by steel and polyethylene and a glove box shielded by leaded acrylic resin, where experimental apparatuses have been equipped and a high purity argon gas atmosphere is maintained. In the facility 10 g of $^{241}$ Am as well as the other TRU of Np, Pu and Cm can be handled. This report summarizes the outline, structure, performance and interior apparatuses of the facility, and is the result of the joint research between the Japan Atomic Energy Research Institute and three electric power companies of Tokyo Electric Power Co., Tohoku Electric Power Co. and the Japan Atomic Power Co.

Journal Articles

Recrystallization by annealing in SiC amorphized with Ne irradiation

Aihara, Jun; Hojo, Kiichi; Furuno, Shigemi*; Ishihara, Masahiro; Hayashi, Kimio

Journal of Electron Microscopy, 51(2), p.93 - 98, 2002/05

https://doi.org/10.1093/jmicro/51.2.93

Times Cited Count：6 Percentile：20.46(Microscopy)

no abstracts in English

Journal Articles

Current status of researches on the plutonium rock-like oxide fuel and its burning in light water reactors

Yamashita, Toshiyuki; Akie, Hiroshi; Nakano, Yoshihiro; Kuramoto, Kenichi; Nitani, Noriko; Nakamura, Takehiko

Progress in Nuclear Energy, 38(3-4), p.327 - 330, 2001/02

https://doi.org/10.1016/S0149-1970(00)00127-X

Times Cited Count：12 Percentile：64.65(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Rock-like oxide fuel and inert matrix fuel

Yamashita, Toshiyuki

Nihon Genshiryoku Gakkai "Kodo Nenryo Gijutsu" Kenkyu Senmon Iinkai Hokokusho, p.467 - 474, 2001/00

no abstracts in English

Journal Articles

Preparation and characterization of PuN pellets containing ZrN and TiN

Arai, Yasuo; Nakajima, Kunihisa

Journal of Nuclear Materials, 281(2-3), p.244 - 247, 2000/10

https://doi.org/10.1016/S0022-3115(00)00393-7

Times Cited Count：40 Percentile：92.08(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Decay heat removal analyses on the heavy liquid metal cooled fast breeding reactor; Comparisons of the decay heat removal characteristics on Lead, Lead-Bismuth and Sodium cooled reactors

Sakai, Takaaki; *; Ohshima, Hiroyuki; Yamaguchi, Akira

JNC TN9400 2000-033, 94 Pages, 2000/04

JNC-TN9400-2000-033.pdf:4.36MB

The feasibility study on several concepts for the commercial fast breeder reactor(FBR) in future has been conducted in JNC for the kinds of possible coolants and fuel types to confirm the direction of the FBR developments in Japan. ln this report, Lead and Lead-Bismuth eutectic coolants were estimated for the decay heat removal characteristics by the comparison with sodium coolant that has excellent features for the heat transfer and heat transport performance. Heavy liquid metal coolants, such as Lead and Lead-Bismuth, have desirable chemical inertness for water and atmosphere. Therefore, there are many economical plant proposals without an intermediate heat transport system that prevents the direct effect on a reactor core by the chemical reaction between water and the liquid metal coolant at the hypocritical tube fairer accidents in a steam generator. ln this study, transient analyses on the thermal-hydraulics have been performed for the decay heat removal events in "Equivalent plant" with the Lead, Lead-Bismuth and Sodium coolant by using Super-COPD code. And a resulted optimized lead cooled plant in feasibility study was also analyzed for the comparison. ln conclusion, it is become clear that the natural circulation performance, that has an important roll in passive safety characteristic of the reactor, is more excellent in heavy liquid metals than sodium coolant during the decay heat removal transients. However, we need to conform the heat transfer reduction by the oxidize film or the corrosion products expected to appear on the heat transfer surface in the Lead and Lead-Bismuth circumstance.

JAEA Reports

Corrosion bihavior of carbon steel in high-temperature sodium compounds; Recommended equation for corrosion rate of the carbon steel in sodium compounds (Na $_{2}$ O $_{2}$ -NaOH System)

Yoshida, Eiichi; Aoto, Kazumi; Hirakawa, Yasushi;

JNC TN9400 2000-024, 42 Pages, 1999/10

JNC-TN9400-2000-024.pdf:1.63MB

For the purpose of improving the reliability of evaluation, the corrosion rate equation of the carbon steel SM400B (JIS G3106) in the high-temperature sodium compounds (NaOH-Na $_{2}$ 0 $_{2}$ system) was revised. ln this revision, the data acquired after 1997 was used. Based on the experimental results, the evaluation was made to be an approach to the following; (1)Metal loss of carbon steel in NaOH-Na $_{2}$ 0 $_{2}$ system was evaluated as increases in exposure to the time, which is linear rate law. (2)There were no significant effects of the experiment atmosphere and mixing speed of the reagent on corrosion rate. (3)The concentration of Na $_{2}$ 0 $_{2}$ in sodium compound is considered for the evaluation. The concentration under experiment is made to be the over concentration necessary for maintaining the dominant reaction between Fe and Na $_{2}$ 20 $_{2}$ . As a result of the evaluation, the additional data are 67 points. The data for the revision of the evaluation equation became the total of 105 points, when existing data of 38 points were added. The statistical evaluation of 105 points was carried out, and following recommended equation was obtained. C $_{R}$ = C exp(-Q/RT) Where; C $_{R}$ : Corrosion rate, mm/h C : Material constant Q : Apparent activation energy, cal/mol R : Gas constant, 1.986 cal/mol K T ; Absolute temperature, K Q = 9.61 kcal/mol C = 148.29 (average), 262.11 (99% UCL), 83.90 (99% LCL)