Refine your search:     
Report No.
 - 
Search Results: Records 1-18 displayed on this page of 18
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Journal Articles

Thermophysical properties of stainless steel containing 5 mass%B$$_{4}$$C in the solid phase

Takai, Toshihide; Furukawa, Tomohiro; Yamano, Hidemasa

Nuclear Technology, 205(9), p.1164 - 1174, 2019/09

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

Journal Articles

Thermophysical properties of stainless steel containing 5mass%-B$$_{4}$$C in the solid phase

Takai, Toshihide; Furukawa, Tomohiro; Yamano, Hidemasa

Proceedings of 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) (CD-ROM), p.1007 - 1013, 2018/04

Journal Articles

Examination of $$^{131}$$I and $$^{137}$$Cs releases during late phase of Fukushima Daiichi NPP accident by using $$^{131}$$I/$$^{137}$$Cs ratio of source terms evaluated reversely by WSPEEDI code with environmental monitoring data

Hidaka, Akihide; Yokoyama, Hiroya

Journal of Nuclear Science and Technology, 54(8), p.819 - 829, 2017/08

AA2016-0500.pdf:0.44MB

 Times Cited Count:8 Percentile:15.68(Nuclear Science & Technology)

To clarify what happened during the Fukushima accident, the phenomena within RPV and the discussion of ties with the environmental monitoring are very important. However, the previous study has not necessarily advanced until the present that passed almost six years from the accident. The present study investigated $$^{131}$$I and $$^{137}$$Cs release behaviors during the late phase of the accident based on $$^{131}$$I/$$^{137}$$Cs ratio of the source terms that were recently evaluated backward by WSPEEDI code based on environmental monitoring data. The $$^{131}$$I release from the contaminated water in the basement of 1F2 and 1F3 reactor buildings was evaluated to be about 10% of $$^{131}$$I source term. The increase in $$^{137}$$Cs release from March 21 to 23 and from March 30 to 31 could be explained by the release of CsBO$$_{2}$$ which is formed as a result of chemical reactions of Cs with B$$_{4}$$C due to re-ascension of the core temperature caused by slight shortage of the core cooling water.

Journal Articles

Basic visualization experiments on eutectic reaction between boron carbide and stainless steel under sodium-cooled fast reactor conditions

Yamano, Hidemasa; Suzuki, Toru; Kamiyama, Kenji; Kudo, Isamu*

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Next Generation Nuclear Systems for Sustainable Development (FR-17) (USB Flash Drive), 11 Pages, 2017/06

This paper describes basic visualization experiments on eutectic reaction and relocation of boron carbide (B$$_{4}$$C) and stainless steel (SS) under a high temperature condition exceeding 1500$$^{circ}$$C as well as the importance of such behaviors in molten core during a core disruptive accident in a Generation-IV sodium-cooled fast reactor (750 MWe class) designed in Japan. At first, a reactivity history was calculated using an exact perturbation calculation tool taking into account expected behaviors. This calculation indicated the importance of a relocation behavior of the B$$_{4}$$C-SS eutectic because its behavior has a large uncertainty in the reactivity history. To clarify this behavior, basic experiments were carried out by visualizing the reaction of a B$$_{4}$$C pellet contacted with molten SS in a high temperature-heating furnace. The experiments have shown the eutectic reaction visualization as well as freezing and relocation of the B$$_{4}$$C-SS eutectic in upper part of the solidified test piece due to the density separation.

JAEA Reports

Boron release kinetics from mixed melts of boron carbide, stainless steel and Zircaloy; A Literature review on the behavior of control rod materials under severe accidents

Di Lemma, F. G.; Miwa, Shuhei; Osaka, Masahiko

JAEA-Review 2016-007, 27 Pages, 2016/03

JAEA-Review-2016-007.pdf:1.88MB

During a nuclear power plant Severe Accident, complex boron melts can be formed, due to interaction of the control rods with the cladding materials. These can affect ultimately the source term assessment. This review will describe the results of previous studies on boron carbide/stainless steel/Zircaloy (B$$_{4}$$C/SS/Zry) melts, which will finally provide guidance for the needs of future experiments. This review showed that models for the behavior of complex B$$_{4}$$C/SS/Zry melts are limited, and unsuccessful in simulating core degradation, thus the improvement of the database for B$$_{4}$$C/SS/Zry melts is needed. Our experimental plan aims in providing thermodynamics and kinetics models for such melts, with the final aim of improving boron modelling in SA codes analysis and of understanding its effect on fission products behavior.

Journal Articles

Diagnostics of pulsed plasma in laser ablation of boron compounds

Oba, Hironori; Saeki, Morihisa; Yokoyama, Atsushi

Proceedings of Plasma Science Symposium 2005/22nd Symposium on Plasma Processing (PSS-2005/SPP-22), p.331 - 332, 2005/01

A plasma produced by a XeCl laser ablation of boron compound was investigated using ion probes and a quadrupole mass spectrometer. Although the ablated neutral boron atoms had a natural abundance ratio, the isotope ratio of singly ionized boron atoms having a greatly different from the natural abundance ratio was observed. The observed isotope ratio of boron ions was different from the natural abundance.

Journal Articles

Sputtering experiments on B$$_{4}$$C doped CFC under high particle flux with low energy

Nakamura, Kazuyuki; Dairaku, Masayuki; Akiba, Masato; Okumura, Yoshikazu

Journal of Nuclear Materials, 241-243, p.1142 - 1146, 1997/00

 Times Cited Count:9 Percentile:38.08

no abstracts in English

Journal Articles

New composite composed of boron carbide and carbon fiber with high thermal conductivity for first wall

*; Saido, Masahiro; Nakamura, Kazuyuki; Akiba, Masato; ; Goto, Yoshitaka*; *; *; Yamaki, Takahiro*; *; et al.

Journal of Nuclear Materials, 233-237(PT.A), p.781 - 786, 1996/00

 Times Cited Count:13 Percentile:25.76(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Delayed neutron emission measurements from fast fission of U-235 and NP-237

W.S.Charlton*; T.A.Parish*; S.Raman*; Shinohara, Nobuo; Ando, Masaki

PHYSOR 96: Int. Conf. on the Physics of Reactors, 3, p.F11 - F20, 1996/00

no abstracts in English

Journal Articles

Thermodynamic analysis of behavior of HTGR fuel and fission products under accidental air or water ingress conditions

Minato, Kazuo; Fukuda, Kosaku

IAEA-TECDOC-784, 0, p.86 - 91, 1995/01

no abstracts in English

Journal Articles

Optimization method of rod-type burnable poisons for nuclear designs of HTGRs

Yamashita, Kiyonobu

Journal of Nuclear Science and Technology, 31(9), p.979 - 985, 1994/09

 Times Cited Count:6 Percentile:46.2(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Compatibility of Heat Resistant Alloys With Boron Carbide,2

; ; ; ;

JAERI-M 82-196, 29 Pages, 1982/12

JAERI-M-82-196.pdf:2.41MB

no abstracts in English

JAEA Reports

Compatibility of Heat Resistant Alloys with Boron Carbide

;

JAERI-M 9185, 20 Pages, 1980/11

JAERI-M-9185.pdf:3.77MB

no abstracts in English

Oral presentation

Basic visualization experiments on eutectic reaction of boron carbide and stainless steel under sodium-cooled fast reactor conditions

Yamano, Hidemasa; Suzuki, Toru; Kamiyama, Kenji; Kudo, Isamu*

no journal, , 

This paper describes basic visualization experiments on eutectic reaction and relocation of boron carbide (B$$_{4}$$C) and stainless steel (SS) under a high temperature condition exceeding 1500$$^{circ}$$C as well as the importance of such behaviors in molten core during a core disruptive accident in a Generation-IV sodium-cooled fast reactor (750 MWe class) designed in Japan. At first, a reactivity history was calculated using an exact perturbation calculation tool taking into account expected behaviors. This calculation indicated the importance of a relocation behavior of the B$$_{4}$$C-SS eutectic because its behavior has a large uncertainty in the reactivity history. To clarify this behavior, basic experiments were carried out by visualizing the reaction of a B$$_{4}$$C pellet contacted with molten SS in a high temperature-heating furnace. The experiments have shown the eutectic reaction visualization as well as freezing and relocation of the B$$_{4}$$C-SS eutectic in upper part of the solidified test piece due to the density separation.

Oral presentation

EPMA analysis of multi-component interaction products between boron carbide and stainless steel under a postulated core disruptive accident in SFR

Nakamura, Kinya*; Ota, Hirokazu*; Takai, Toshihide; Yamano, Hidemasa

no journal, , 

To investigate in-depth redistribution behavior of the constituent elements of B$$_{4}$$C and SS, electron probe microanalysis was applied to the multi-component interaction products held at 1500$$^{circ}$$C for 8 min approximately in argon gas atmosphere in this study. The results indicated that relatively low-density boron was preferentially diffused the upper surface of the molten SS horizontally to form acicular and high melting point compound (Cr,Fe)$$_{2}$$B along with the eutectic microstructure composed of (Fe,Cr,Ni) solid solution and (Cr,Fe)$$_{2}$$B. According to the macroscopic quantitative analysis, average chemical concentration of boron is almost uniform in the horizontal direction regardless of the distance from the B$$_{4}$$C pellet but decreased toward the bottom in the molten SS monotonously in the vertical direction.

Oral presentation

Thermophysical properties of stainless steel containing 10mass%-B$$_{4}$$C in the solid state

Takai, Toshihide; Furukawa, Tomohiro; Yamano, Hidemasa

no journal, , 

18 (Records 1-18 displayed on this page)
  • 1