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.

Research plan on in-vessel debris coolability in ALPHA program

Maruyama, Yu; Yamano, Norihiro; Kudo, Tamotsu; Moriyama, Kiyofumi; Sugimoto, Jun

JAERI-memo 08-127, p.269 - 275, 1996/06

no abstracts in English

Gamma spectrometry of TMI-2 debris

Uetsuka, Hiroshi; Nagase, Fumihisa;

JAERI-Research 95-084, 36 Pages, 1995/11

JAERI-Research-95-084.pdf:1.32MB

no abstracts in English

Three-dimensional thermal stress analyses for the TMI-2 vessel lower head using finite element method

Onizawa, Kunio; Hashimoto, Kazuichiro

OECD Documents, Three Mile Island Reactor Pressure Vessel Investigation Project; Achievements and, 0, p.322 - 334, 1995/00

no abstracts in English

A Method for estimating peak temperature reached of the TMI-2 vessel lower head by microstructural examination of 308 stainless steel overlay

Tsukada, Takashi; Suzuki, Masahide; Kawasaki, Satoru

Proceedings of Three Mile Island Reactor Pressure Vessel Investigation Project Open Forum, p.151 - 163, 1994/00

no abstracts in English

Results and lessons from the accident study and recovery actions for TMI-2; Introduction to TMI special volume of the Nuclear Technology

JAERI-M 93-111, 464 Pages, 1993/06

JAERI-M-93-111.pdf:20.79MB

no abstracts in English

Hydrogen generation during reflooding of degraded core as an accident management measure

Hidaka, Akihide; Sugimoto, Jun; Soda, Kunihisa

EUR-14039-EN, p.28 - 36, 1992/00

no abstracts in English

Results of OECD LOFT program

Nihon Genshiryoku Gakkai-Shi, 33(12), p.1112 - 1120, 1991/12

https://doi.org/10.3327/jaesj.33.1112

no abstracts in English

Thermal response analyses of the Three Mile Island Unit 2 reactor pressure vessel

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

Transactions of the 11th Int. Conf. on Structural Mechanics in Reactor Technology,Vol. F, p.123 - 128, 1991/08

no abstracts in English

Thermal-hydraulic analysis of the initial phase of the Three Mile Island Unit 2 accident

Hashimoto, Kazuichiro; Soda, Kunihisa;

Nuclear Technology, 87, p.1058 - 1066, 1989/12

https://doi.org/10.13182/NT89-A27697

no abstracts in English