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Journal Articles

In-depth analysis for uncertain phenomena on fission product transport in the OECD/NEA ARC-F project

Lind, T.*; Herranz, L. E.*; Sonnenkalb, M.*; Maruyama, Yu

Proceedings of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) (Internet), 15 Pages, 2022/03

Journal Articles

Development and testing of a delayed gamma-ray spectroscopy instrument utilizing Cf-252 neutrons evaluated for nuclear safeguards applications

Rodriguez, D.; Abbas, K.*; Koizumi, Mitsuo; Nonneman, S.*; Rossi, F.; Takahashi, Tone

Nuclear Instruments and Methods in Physics Research A, 1014, p.165685_1 - 165685_10, 2021/10

Journal Articles

Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), Phase 2; Results of severe accident analyses for unit 3

Lind, T.*; Pellegrini, M.*; Herranz, L. E.*; Sonnenkalb, M.*; Nishi, Yoshihisa*; Tamaki, Hitoshi; Cousin, F.*; Fernandez Moguel, L.*; Andrews, N.*; Sevon, T.*

Nuclear Engineering and Design, 376, p.111138_1 - 111138_12, 2021/05

 Times Cited Count:3 Percentile:81.22(Nuclear Science & Technology)

This is the third part of the three part paper describing the accidents at the FDNPS as analyzed in the Phase 2 of the OECD/NEA project "Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Plant" (BSAF). In this paper, we describe the accident progression in unit 3. In the BSAF project, eight organizations from five countries analyzed severe accident scenarios for Unit 3 at the Fukushima Daiichi site using different severe accident codes. The present paper for Unit 3 describes the findings of the comparison of the participants' results against each other and against plant data, the evaluation of the accident progression and the final status inside the reactors. Special focus is on the status of the reactor pressure vessel, melt release and fission product release and transport. Unit 3 specific aspects, e.g., the complicated accident progression following repeated containment venting actuations and attempts at coolant injection at the time of the major core degradation, are highlighted and points of consensus as well as remaining uncertainties and data needs will be summarized. FP transport is analyzed, and the calculation results are compared with dose rate measurements in the containment. The release of I-131 and Cs-137 to the environment is compared with analysis conducted by using WSPEEDI code.

Journal Articles

Evaluation of high-energy delayed gamma-ray spectra dependence on interrogation timing patterns

Rodriguez, D.; Bogucarska, T.*; Koizumi, Mitsuo; Lee, H.-J.; Pedersen, B.*; Rossi, F.; Takahashi, Tone; Varasano, G.*

Nuclear Instruments and Methods in Physics Research A, 997, p.165146_1 - 165146_13, 2021/05

 Times Cited Count:1 Percentile:0.03(Instruments & Instrumentation)

Journal Articles

Phenomena identification ranking tables for accident tolerant fuel designs applicable to severe accident conditions

Khatib-Rahbar, M.*; Barrachin, M.*; Denning, R.*; Gabor, J.*; Gauntt, R.*; Herranz, L. E.*; Hobbins, R.*; Jacquemain, D.*; Maruyama, Yu; Metcalf, J.*; et al.

NUREG/CR-7282, ERI/NRC 21-204 (Internet), 160 Pages, 2021/04

JAEA Reports

Basic research on the stability of fuel debris including alloy phase (Contract research); FY2019 Nuclear Energy Science & Technology and Human Resource Development Project

Collaborative Laboratories for Advanced Decommissioning Science; Tohoku University*

JAEA-Review 2020-032, 97 Pages, 2021/01

JAEA-Review-2020-032.pdf:4.16MB

The Collaborative Laboratories for Advanced Decommissioning Science (CLADS), Japan Atomic Energy Agency (JAEA), had been conducting the Nuclear Energy Science & Technology and Human Resource Development Project (hereafter referred to "the Project") in FY2019. The Project aims to contribute to solving problems in the nuclear energy field represented by the decommissioning of the Fukushima Daiichi Nuclear Power Station, Tokyo Electric Power Company Holdings, Inc. (TEPCO). For this purpose, intelligence was collected from all over the world, and basic research and human resource development were promoted by closely integrating/collaborating knowledge and experiences in various fields beyond the barrier of conventional organizations and research fields. The sponsor of the Project was moved from the Ministry of Education, Culture, Sports, Science and Technology to JAEA since the newly adopted proposals in FY2018. On this occasion, JAEA constructed a new research system where JAEA-academia collaboration is reinforced and medium-to-long term research/development and human resource development contributing to the decommissioning are stably and consecutively implemented. Among the adopted proposals in FY2018, this report summarizes the research results of the "Basic Research on the Stability of Fuel Debris Including Alloy Phase" conducted in FY2019. In the present study, we focus on fuel debris consisting of oxide phase and alloy phase generated by the high-temperature chemical reaction between structure materials (SUS pipes, pressure vessels, etc.) and fuels (melted fuels, claddings components, etc.). We synthesize the simulated debris of UO$$_{2}$$-SUS system and UO$$_{2}$$-Zr(ZrO$$_{2}$$)-SUS system by high-temperature heat treatment, and measure their chemical property and dissolution behavior in water. Also, we will conduct research and development to spectroscopically analyze secular changes of oxide phase and alloy phase in the simulated debris.

JAEA Reports

Basic research on the stability of fuel debris including alloy phase (Contract research); FY2018 Center of World Intelligence Project for Nuclear Science/Technology and Human Resource Development

Collaborative Laboratories for Advanced Decommissioning Science; Tohoku University*

JAEA-Review 2019-035, 61 Pages, 2020/03

JAEA-Review-2019-035.pdf:2.9MB

JAEA/CLADS, had been conducting the Center of World Intelligence Project for Nuclear Science/Technology and Human Resource Development (hereafter referred to "the Project") in FY2018. The Project aims to contribute to solving problems in nuclear energy field represented by the decommissioning of the Fukushima Daiichi Nuclear Power Station, Tokyo Electric Power Company Holdings, Inc. For this purpose, intelligence was collected from all over the world, and basic research and human resource development were promoted by closely integrating/collaborating knowledge and experiences in various fields beyond the barrier of conventional organizations and research fields. The sponsor of the Project was moved from the Ministry of Education, Culture, Sports, Science and Technology to JAEA since the newly adopted proposals in FY2018. On this occasion, JAEA constructed a new research system where JAEA-academia collaboration is reinforced and medium-to-long term research/development and human resource development contributing to the decommissioning are stably and consecutively implemented. Among the adopted proposals in FY2018, this report summarizes the research results of the "Basic Research on the Stability of Fuel Debris Including Alloy Phase". In the present study, we focus on fuel debris consisting of oxide phase and alloy phase generated by the high-temperature chemical reaction between structure materials (SUS pipes, pressure vessels, etc.) and fuels (melted fuels, claddings components, etc.). We synthesize the simulated debris of UO$$_{2}$$-SUS system and UO$$_{2}$$-Zr(ZrO$$_{2}$$)-SUS system by high-temperature heat treatment, and measure their chemical property and dissolution behavior in water. Also, we will conduct research and development to spectroscopically analyze secular changes of oxide phase and alloy phase in the simulated debris.

Journal Articles

Influence of chemical speciation in reactor cooling system on pH of suppression pool during BWR severe accident

Shiotsu, Hiroyuki; Ishikawa, Jun; Sugiyama, Tomoyuki; Maruyama, Yu

Journal of Nuclear Science and Technology, 55(4), p.363 - 373, 2018/04

 Times Cited Count:3 Percentile:33.17(Nuclear Science & Technology)

Journal Articles

Bayesian optimization analysis of containment-venting operation in a Boiling Water Reactor severe accident

Zheng, X.; Ishikawa, Jun; Sugiyama, Tomoyuki; Maruyama, Yu

Nuclear Engineering and Technology, 49(2), p.434 - 441, 2017/03

 Times Cited Count:2 Percentile:28.88(Nuclear Science & Technology)

Journal Articles

Experimental investigation of the influence of Mo contained in stainless steel on Cs chemisorption behavior

Di Lemma, F. G.; Nakajima, Kunihisa; Yamashita, Shinichiro; Osaka, Masahiko

Journal of Nuclear Materials, 484, p.174 - 182, 2017/02

 Times Cited Count:15 Percentile:90.26(Materials Science, Multidisciplinary)

Chemisorption phenomena can affect fission products retention in the nuclear reactor vessel during a Severe Accident (SA). This paper will describe the influence of molybdenum contained in type 316 stainless steel (SS) on Cs chemisorption. Our experiments showed the formation of Cs-Mo compounds in addition to CsFeSiO$$_{4}$$, observed previously on SS304. The results of high temperature stability tests on the deposits are also presented. These tests aimed at simulating the revaporization of FP from structural materials during a SA. From our results, it can be inferred that Cs-Mo deposits may revaporize, contributing as a delayed source to the radioactive release.

Journal Articles

Bayesian optimization analysis of containment venting operation in a BWR severe accident

Zheng, X.; Ishikawa, Jun; Sugiyama, Tomoyuki; Maruyama, Yu

Proceedings of 13th Probabilistic Safety Assessment and Management Conference (PSAM-13) (USB Flash Drive), 10 Pages, 2016/10

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.

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

Analysis of pressure- and temperature- induced steam generator tube rupture during PWR severe accident initiated from station blackout

Hidaka, Akihide; Maruyama, Yu; Nakamura, Hideo

Proceedings of 6th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operations and Safety (NUTHOS-6) (CD-ROM), 15 Pages, 2004/00

Severe accident studies showed that Direct Containment Heating issue was resolved for PWRs because a creep rupture at pressurizer surge line would occur prior to the melt-through of Reactor Pressure Vessel during station blackout (TMLB'). However, it was recently concerned that, if the secondary system is depressurized during TMLB', the creep rupture at SG U-tubes would occur earlier than the surge line. This pressure- and temperature-induced SG U-tube rupture (PTI-SGTR) is not preferable because of the increase in offsite consequences. The SCDAP/RELAP5 analyses by USNRC showed that the surge line would fail earlier than the U-tubes. However, the analyses used a coarse nodilization for steam mixing at the SG inlet plenum that could affect the temperature of U-tubes. To investigate the effect of steam mixing, an analysis was performed with MELCOR1.8.4. The analysis showed that the surge line would fail earliest during TMLB' while the U-tubes could fail earliest during TMLB' with secondary system depressurization. Further investigation is needed for occurrence conditions of PTI-SGTR.

Journal Articles

Maintenance methods and procedures for the power conversion system of the Gas Turbine High Temperature Reactor 300 (GTHTR300)

Kosugiyama, Shinichi; Takei, Masanobu; Takizuka, Takakazu; Takada, Shoji; Yan, X.; Kunitomi, Kazuhiko

Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(4), p.532 - 545, 2003/12

no abstracts in English

Journal Articles

The JAERI-KEK joint RIB project

Takeuchi, Suehiro

AIP Conference Proceedings 680, p.229 - 236, 2003/00

JAERI and KEK-Institute of Particle and Nuclear Studies are collabarating to build an ISOL-type radioactive ion beam(RIB) acceleration system in the JAERI-Tokai tandem accelerator lab. In this project, the tandem accelerator is used as a proton beam driver to create RIB from fission products of a uranium target and a RIB accelerator already built by KEK will be installed in an old target room of the tandem accelerator lab. The beam energy is 1.1 MeV/nucleon, which is not sufficient for experiments related to nuclear reactions. They have a plan to boost the beams to 5 - 9 MeV/u by developing a pre-booster and using existing super-conducting tandem-booster. The plan of this project, acceleration divices and present status will be outlined in the RIB session of the CAARI.

Journal Articles

Conceptual design study of the transmutation experimental facilities

Sasa, Toshinobu; Oigawa, Hiroyuki; Kikuchi, Kenji; Ikeda, Yujiro

Proceedings of American Nuclear Society Conference "Nuclear Applications in the New Millennium" (AccApp-ADTTA '01) (CD-ROM), 7 Pages, 2002/00

A design study of the accelerator-driven system (ADS) for transmutation of minor actinides and long-lived fission products has been performed at Japan Atomic Energy Research Institute (JAERI) under the national OMEGA program. To solve the technical issues related to the ADS development, a transmutation experimental facility (TEF) is planned to bulid under the JAERI-High Energy Accelerator Research Organization joint project. The TEF consists of two facilities, Transmutation Physics Experimental Facility and Transmutation Engineering Experimental Facility. Proton beams of 600 MeV and 0.3 mA are to be delivered to this facility. The presentation describes a conceptual design study of the TEF.

Journal Articles

Social acceptability and scientific prospect of fusion energy, 7; Safety

Seki, Yasushi

Purazuma, Kaku Yugo Gakkai-Shi, 74(8), p.795 - 801, 1998/08

no abstracts in English

Journal Articles

Physical features of target and blanket

IAEA-TECDOC-985, 0, p.32 - 43, 1997/11

no abstracts in English

JAEA Reports

Analytical results of radiochemistry of the JRR-3M

;

JAERI-Tech 97-029, 47 Pages, 1997/07

JAERI-Tech-97-029.pdf:1.82MB

no abstracts in English

74 (Records 1-20 displayed on this page)