検索対象:     
報告書番号:
※ 半角英数字
 年 ~ 
 年
検索結果: 6 件中 1件目~6件目を表示
  • 1

発表形式

Initialising ...

選択項目を絞り込む

掲載資料名

Initialising ...

発表会議名

Initialising ...

筆頭著者名

Initialising ...

キーワード

Initialising ...

使用言語

Initialising ...

発行年

Initialising ...

開催年

Initialising ...

選択した検索結果をダウンロード

論文

EBR-II passive safety demonstration tests benchmark analyses; Phase 2

Briggs, L.*; Monti, S.*; Hu, W.*; Sui, D.*; Su, G. H.*; Maas, L.*; Vezzoni, B.*; Partha Sarathy, U.*; Del Nevo, A.*; Petruzzi, A.*; et al.

Proceedings of 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) (USB Flash Drive), p.3030 - 3043, 2015/08

IAEA主催の「EBR-II炉停止のための熱除去試験に係るベンチマーク解析」研究共同プロジェクトは4年計画のうち3年目となっている。本プロジェクトには11ヶ国19機関がEBR-IIで行われた炉停止のための熱除去試験の内最も厳しい過渡試験の内の2ケースについて解析を実施してきた。ベンチマーク仕様に基づき炉心及び1次主冷却系の解析モデルを構築し解析を実施した。本プロジェクトのPhese 1ではブラインド解析が実施され測定データと比較・評価された。Phase 2では、Phese 1で試験データと合わなかった箇所を検討し解析モデルの改良を実施した。本論文では、最新の解析結果及び残された作業の実施方針を記載した。

論文

IAEA NAPRO Coordinated Research Project; Physical properties of sodium

Passerini, S.*; Carardi, C.*; Grandy, C.*; Azpitarte, O. E.*; Chocron, M.*; Japas, M. L.*; Bubelis, E.*; Perez-Martin, S.*; Jayaraj, S.*; Roelofs, F.*; et al.

Proceedings of 2015 International Congress on Advances in Nuclear Power Plants (ICAPP 2015) (CD-ROM), p.780 - 790, 2015/05

The IAEA recently established a CRP on "Sodium properties and safe operation of experimental facilities in support of the development and deployment of Sodium Cooled Fast Reactors - NAPRO", to be carried out in the period 2013 - 2017. The first phase of the CRP is focused on the collection and assessment of sodium properties, and it will lead to a consistent property data set which will be published in the form of a handbook. This work is carried out by the 11 participating organizations from 10 Member States through the review and evaluation of the existing available data, the identification of the data gaps and the development of recommendations for experimental programmes to support closing these data gaps. A specific work package (WP 1.1), under the leadership of Argonne National Laboratory, is focused on the analysis of physical properties of sodium: thermodynamic properties and transport properties. The expected outcome includes the improved understanding of the availability, accuracy and range of applications of sodium properties centered on fast reactors and other technological applications. The implemented methodology for WP 1.1 is described and so the properties included in WP 1.1 and their classification. Major findings to date related to WP 1.1 are presented in this work, including detailed analysis of two selected properties.

論文

IAEA benchmark calculations on control rod withdrawal test performed during Phenix End-of-Life experiments; Benchmark results and comparisons

Pascal, V.*; Prulhi$`e$re, G.*; Vanier, M.*; Fontaine, B.*; Devan, K.*; Chellapandi, P.*; Kriventsev, V.*; Monti, S.*; Mikityuk, K.*; Chenu, A.*; et al.

Proceedings of International Conference on the Physics of Reactors; The Role of Reactor Physics toward a Sustainable Future (PHYSOR 2014) (CD-ROM), 16 Pages, 2014/09

2009年に仏Phenix炉のEnd of Life試験において、定格出力時における制御棒の非対称引抜が径方向出力分布に与える影響を目的とする「制御棒引抜試験」が実施された。IAEAのTWG-FR(高速炉技術作業部会)において本試験に対するベンチマーク解析を実施するための共同研究プロジェクト(CRP)が立ち上げられ、CEA, ANL, IGCAR, IPPE, IRSN,原子力機構, KIT, PSIから専門家が参加し本CRPを進めている。ここでは、「制御棒引抜試験」の概要及び制御棒非対称引抜に伴う出力分布変化に対する測定結果について述べるとともに、本CRPにて得られた解析結果を基に、測定結果との差及び解析結果同士の差の要因について考察する。

論文

Benchmark analyses on the control rod withdrawal tests performed during the PH$'E$NIX end-of-life experiments

Monti, S.*; Toti, A.*; Stanculescu, A.*; Pascal, V.*; Fontaine, B.*; Herrenschmidt, A.*; Prulhiere, G.*; Vanier, M.*; Varaine, F.*; Vasile, A.*; et al.

IAEA-TECDOC-1742, 247 Pages, 2014/06

Before the definitive shutdown in 2009, PH$'E$NIX end-of-life tests were conducted to gather additional experience on the operation of sodium cooled reactors. Thanks to the CEA, the IAEA decided in 2007 to launch the CRP entitled Control Rod Withdrawal Test performed during the PH$'E$NIX end-of-life experiments. The objective of this publication is to document the results and main achievements of the benchmark analyses on the control rod withdrawal test performed within the framework. For the total control rod worth, two groups of results were observed. The difference between the groups can be explained on the basis of the control rod model treatment on self-shielded cross-sections of absorbing media with deterministic codes. Heat transfers and sodium mixing phenomena strengthened by sodium turbulent flows in the hot plenum disturb power balances and degrade the comparisons. It leads the systematic overestimation in power deviation calculations for all the participants.

論文

A New IAEA coordinated research project on sodium properties and safe operation of experimental facilities in support of the development and deployment of sodium-cooled fast reactors

Monti, S.*; Latge, C.*; Long, B.*; Azpitarte, O. E.*; Chellapandi, P.*; Stieglitz, R.*; Eckert, S.*; 大平 博昭; Lee, J.*; Roelofs, F.*; et al.

Proceedings of 2014 International Congress on the Advances in Nuclear Power Plants (ICAPP 2014) (CD-ROM), p.474 - 481, 2014/04

In order to address some inconsistencies regarding sodium physical and chemical properties, and internationally agreed standard rules for designing sodium experimental facilities, good practices and safety guidelines, the IAEA recently established a CRP on "Sodium properties and safe operation of experimental facilities in support of the development and deployment of Sodium Cooled Fast Reactors - NAPRO", to be carried out in the period 2013 - 2017. The CRP will be focused on the collection and assessment of sodium properties, and it will lead to a consistent property data set which will be published in the form of a handbook. This work will be carried out by the 11 participating organizations from 10 Member States through the review and evaluation of the existing available data, the identification of the data gaps and the development of recommendations for experimental programmes to support closing these data gaps. The CRP will also focus on the definition of design rules and best practice for sodium experimental facilities and guidelines for the safe handling of sodium, which poses hazard due to its chemical reactivity with water and air. Outcomes of this part of the CRP will include shared functional requirements, good practices, codes and standards and safety criteria for the design, construction and operation of experimental Na loops in support of innovative SFR.

論文

Benchmark calculations on control rod withdrawal tests performed during Phenix End-of-Life experiments

Pascal, V.*; Prulhi$`e$re, G.*; Fontaine, B.*; Devan, K.*; Chellapandi, P.*; Kriventsev, V.*; Monti, S.*; Mikityuk, K.*; Semenov, M.*; Taiwo, T.*; et al.

Proceedings of 2013 International Congress on Advances in Nuclear Power Plants (ICAPP 2013) (USB Flash Drive), 11 Pages, 2013/04

2009年に仏Phenix炉のEnd-of-Life試験において、定格出力時における制御棒の非対称引抜が径方向出力分布に与える影響を把握することを目的とする「制御棒引抜試験」が実施された。IAEAのTWG-FR(高速炉技術作業部会)において本試験に対するベンチマーク解析を実施するための共同研究プロジェクト(CRP)が立ち上げられ、CEA, ANL, IGCAR, IPPE, IRSN, JAEA, KIT, PSIから専門家が参加し、本CRPを進めている。ここでは「制御棒引抜試験」の概要及び制御棒非対称引抜に伴う出力分布変化に対する測定結果について述べるとともに、本CRPにて得られた解析結果をもとに、測定結果との差及び解析結果同士の差の要因について考察する。

6 件中 1件目~6件目を表示
  • 1