Refine your search:     
Report No.
Search Results: Records 1-10 displayed on this page of 10
  • 1

Presentation/Publication Type

Initialising ...


Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...


Initialising ...


Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Review of Fukushima Daiichi Nuclear Power Station debris endstate location in OECD/NEA preparatory study on analysis of fuel debris (PreADES) project

Nakayoshi, Akira; Rempe, J. L.*; Barrachin, M.*; Bottomley, D.; Jacquemain, D.*; Journeau, C.*; Krasnov, V.; Lind, T.*; Lee, R.*; Marksberry, D.*; et al.

Nuclear Engineering and Design, 369, p.110857_1 - 110857_15, 2020/12

 Times Cited Count:0 Percentile:0.33(Nuclear Science & Technology)

Much is still not known about the end-state of core materials in each of the units at Fukushima Daiichi Nuclear Power Station (Daiichi) that were operating on March 11, 2011. The Nuclear Energy Agency of the Organization for Economic Development has launched the Preparatory Study on Analysis of Fuel Debris (PreADES) project as a first step to reduce some of these uncertainties. As part of the PreADES Task 1, relevant information was reviewed to confirm the accuracy of graphical depictions of the debris endstates at the damaged Daiichi units, which provides a basis for suggesting future debris examinations. Two activities have been completed within the PreADES Task 1. First, relevant knowledge from severe accidents at the Three Mile Island Unit 2 and the Chernobyl Nuclear Power Plant Unit 4 was reviewed, along with results from prototypic tests and hot cell examinations, to glean insights that may inform future decommissioning activities at Daiichi. Second, the current debris endstate diagrams for the damaged reactors at Daiichi were reviewed to confirm that they incorporate relevant knowledge from plant observations and from severe accident code analyses of the BSAF (Benchmark Study of the Accident at Daiichi Nuclear Power Station) 1 and 2 projects. This paper highlights Task 1 insights, which have the potential to not only inform future Decontamination and Decommissioning activities at Daiichi, but also provide important perspectives for severe accident analyses and management, particularly regarding the long term management of a damaged nuclear site following a severe accident.

Journal Articles

New research programme of JAEA/CLADS to reduce the knowledge gaps revealed after an accident at Fukushima-1; Introduction of boiling water reactor mock-up assembly degradation test programme

Pshenichnikov, A.; Kurata, Masaki; Bottomley, D.; Sato, Ikken; Nagae, Yuji; Yamazaki, Saishun

Journal of Nuclear Science and Technology, 57(4), p.370 - 379, 2020/04

 Times Cited Count:6 Percentile:71.03(Nuclear Science & Technology)

Journal Articles

Oxidation kinetics of silicon carbide in steam at temperature range of 1400 to 1800$$^{circ}$$C studied by laser heating

Pham, V. H.; Nagae, Yuji; Kurata, Masaki; Bottomley, D.; Furumoto, Kenichiro*

Journal of Nuclear Materials, 529, p.151939_1 - 151939_8, 2020/02


 Times Cited Count:2 Percentile:62.87(Materials Science, Multidisciplinary)

Journal Articles

Current situation of OECD/NEA, Preparatory Study on Analysis of Fuel debris (PreADES) project

Nakayoshi, Akira; Journeau, C.*; Rempe, J.*; Barrachin, M.*; Bottomley, D.; Nauchi, Y.*; Song, J. H.*

Proceedings of 2019 International Workshop on Post-Fukushima Challenges on Severe Accident Mitigation and Research Collaboration (SAMRC 2019) (USB Flash Drive), 6 Pages, 2019/11

Journal Articles

A Review of revaporisation behaviour of radioactive Cs deposits and its impact on the source term in severe nuclear accidents from Ph$'e$bus FP results and single effect testing

Knebel, K.*; Jokiniemi, J.*; Bottomley, D.

Journal of Nuclear Science and Technology, 56(9-10), p.772 - 789, 2019/09

 Times Cited Count:4 Percentile:62.24(Nuclear Science & Technology)

Revaporisation of the fission products deposited in the primary circuit of a reactor was identified as a possible late source of fission product release during a severe accident: eg. loss of coolant accident (LOCA). Subsequent testing has shown that revaporisation is very likely to occur given a breach of the reactor and is an important contributor for the source term release to the containment and biosphere. The first part reviews the revaporisation mechanisms of Cs and other volatile or semi-volatile fission products transported in the primary circuit that were derived from the Phebus FP and associated programmes. The second part examines the separate effects testing to determine the high temperature chemistry ofvolatile and semi-volatile fission products (I, Mo, Ru) and structural materials (Ag, B) as well as atmospheric effects which substantially affect the source term. Finally, it examines Cs data from reactor accident sites that is providing additional knowledge of longer-term fission product chemistry. The results have been summarised in the form of a table and schematic diagram. This accumulated knowledge and experience has important applications to minimising contamination during decommissioning and site remediation techniques, as well as improving SA simulation codes and raising nuclear safety.

Journal Articles

Features of a control blade degradation observed ${it in situ}$ during severe accidents in boiling water reactors

Pshenichnikov, A.; Yamazaki, Saishun; Bottomley, D.; Nagae, Yuji; Kurata, Masaki

Journal of Nuclear Science and Technology, 56(5), p.440 - 453, 2019/05

 Times Cited Count:7 Percentile:85.54(Nuclear Science & Technology)

Journal Articles

Current situation of OECD/NEA, Preparatory Study on Analysis of Fuel debris (PreADES) project

Nakayoshi, Akira; Bottomley, D.; Washiya, Tadahiro

Proceedings of 56th Annual Meeting on Hot Laboratories and Remote Handling (HOTLAB 2019) (Internet), 3 Pages, 2019/00

Journal Articles

Release and transport behaviors of non-gamma-emitting fission products and actinides in steam and hydrogen atmospheres

Miwa, Shuhei; Ducros, G.*; Hanus, E.*; Bottomley, P. D. W.*; Van Winckel, S.*; Osaka, Masahiko

Nuclear Engineering and Design, 326, p.143 - 149, 2018/01

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

The release and transport behaviors of 13 non-gamma-emitting fission products (FPs) and actinides in steam and hydrogen atmospheres were investigated based on the chemical analysis of their deposits on the components of VERCORS test loops. The new findings were obtained; strontium release was significantly enhanced in hydrogen atmosphere and a part of released strontium was transported towards the lower temperature region, uranium release was enhanced in steam atmosphere but most of released uranium deposited at high temperature region.

Journal Articles

Upgrading the experimental database of fission products and actinides release behaviour in the VERCORS program through chemical analysis

Miwa, Shuhei; Ducros, G.*; Hanus, E.*; Bottomley, P. D. W.*; Van Winckel, S.*

Proceedings of 7th European Review Meeting on Severe Accident Research (ERMSAR 2015) (Internet), 11 Pages, 2015/03

The release behaviour of $$alpha$$-ray emitters, $$beta$$-ray emitters and stable nuclide from the degraded fuel in the fission product (FP) and actinide release and transport tests, VERCORS tests, were investigated based on the chemical analysis of their deposits on the components of VERCORS test loops. The release of Sr which has a significant public impact shows the possibility to be enhanced in reducing atmosphere. The release of U was significantly enhanced in steam atmosphere, but almost all the released U remained near the fuel. The release behaviour of other non-$$gamma$$-ray emitters such as Rb, Pd, Tc and Pu shows the good consistency with the expectation based on the previous VERCORS tests results. The experimental database of the FP and actinide release behaviour was upgraded through the chemical analysis in terms of the effects of atmosphere on the release behaviour of $$alpha$$-ray emitters, $$beta$$-ray emitters and stable nuclide.

Oral presentation

Evaluation of FP chemistry under severe accident conditions with focuses on the effects of BWR control material, 2; Effect of atmosphere on the FP release and transport behavior

Miwa, Shuhei; Osaka, Masahiko; Ducros, G.*; Hanus, E.*; Bottomley, P. D. W.*; Van Winckel, S.*

no journal, , 

The analysis method of fission product (FP) chemistry for the precise evaluation of the effect of atmosphere on the FP release and transport was investigated by using the results of FP release and transport experiments VERCORS which were carried out at various atmosphere. The results of pseudo chemical kinetics calculation show good consistency with experimental results of FP chemistry in the transport at relative low temperature.

10 (Records 1-10 displayed on this page)
  • 1