Revaluation of hydrogen generation by water radiolysis in SDS vessels at TMI-2 accident

Nagaishi, Ryuji; Morita, Keisuke; Yamagishi, Isao; Hino, Ryutaro; Ogawa, Toru

Proceedings of 2014 Nuclear Plant Chemistry Conference (NPC 2014) (USB Flash Drive), 9 Pages, 2014/10

BB2014-1745.pdf:0.92MB

Two years after Three Mile Island Unit 2 (TMI-2) loss-of-coolant accident, radioactive contaminated water has been processed by Submerged Demineralizer System (SDS) with two types of zeolite adsorbents to remove radioactive nuclides. During and after the process, adsorption amount and distribution of nuclides on the zeolites, residual water content and thermal conductivity in the SDS vessels have been measured or estimated for verification of safety in the process, subsequent transportation and disposal. Hydrogen generation has been also evaluated mainly by direct monitoring in the large-scale of vessel after the process. In this work, the revaluation of hydrogen generation was demonstrated on the basis of the open information of vessel, and the latest experimental data obtained in adsorption and radiolysis occurring in small-scale of zeolite-water mixtures. As a result, the evaluated data was found to be comparable with the reported data obtained in the large-scale of real vessel.

Visualization of simulated molten-fuel behavior in a pressure vessel lower head using high-frame-rate neutron radiography

Nakamura, Hideo; Shibamoto, Yasuteru; Anoda, Yoshinari; Kukita, Yutaka*; Mishima, Kaichiro*; Hibiki, Takashi*

Nuclear Technology, 125(2), p.213 - 224, 1999/02

https://doi.org/10.13182/NT99-A2943

no abstracts in English

High-frame-rate video visualization of simulated lower head behavior during TMI accident using neutron radioscopy

Nakamura, Hideo; Shibamoto, Yasuteru; Anoda, Yoshinari; Kukita, Yutaka; Mishima, Kaichiro*; Hibiki, Takashi*

Fifth World Conf. on Neutron Radiography, 0, p.665 - 672, 1996/00

no abstracts in English

Core melt behaviors and thermal properties in LWR severe accident

Sugimoto, Jun; Uetsuka, Hiroshi; Hidaka, Akihide; Maruyama, Yu; Yamano, N.; Hashimoto, Kazuichiro

Thermophysical Properties 17 (17th Japan Symp. 1996), 0, p.163 - 166, 1996/00

no abstracts in English

Validation of COSTA on predicting core damage accident progression with the TMI-2 accident data

Ishigami, Tsutomu

Journal of Nuclear Science and Technology, 32(7), p.691 - 701, 1995/07

https://doi.org/10.3327/jnst.32.691

no abstracts in English

Present status of research related to in-vessel debris coolability and experimental plan in ALPHA program at JAERI

Maruyama, Yu; Yamano, N.; Kudo, Tamotsu; Moriyama, Kiyofumi; Sugimoto, Jun

Proc., Seminar on the Vapor Explosions in Nuclear Power Safety,Kanzanji 1995, 0, p.54 - 69, 1995/00

no abstracts in English

Companion sample examination and related study at JAERI

Uetsuka, Hiroshi; Nagase, Fumihisa

Proceedings of Three Mile Island Reactor Pressure Vessel Investigation Project Open Forum, p.269 - 280, 1994/00

no abstracts in English

Fuel Reliability Laboratory

Furuta, Teruo

Kaku Nenryo, (17), p.17_44 - 17_45, 1992/06

no abstracts in English

Thermal and stress analyses of the reactor pressure vessel lower head of the Three Mile Island Unit 2

Hashimoto, Kazuichiro; Onizawa, Kunio; Kurihara, Ryoichi; Kawasaki, Satoru; Soda, Kunihisa

Int. J. Press. Vessels Piping, 52, p.25 - 40, 1992/00

https://doi.org/10.1016/0308-0161(92)90057-M

no abstracts in English

Thermal-hydraulic analysis of the Three Mile Island Unit 2 Reactor accident with THALES code

Hashimoto, Kazuichiro; Soda, Kunihisa

JAERI-M 91-193, 21 Pages, 1991/10

JAERI-M-91-193.pdf:0.63MB

no abstracts in English