نتائج البحث - "Erina Hamase"

1

Academic Journal

Development of core design optimization process by integrated analysis with neutronics and plant dynamics

المؤلفون: Erina HAMASE, Kazuki KUWAGAKI, Norihiro DODA, Kenji YOKOYAMA, Masaaki TANAKA

المصدر: Mechanical Engineering Journal. 2024, 11(2):23-00440

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2

Academic Journal

STUDY ON MEASUREMENT METHOD OF DEGREE OF DIFFERENCE IN VALIDATION OF NUMERICAL ANALYSIS FOR DECAY HEAT REMOVAL IN SODIUM-COOLED FAST REACTOR

المؤلفون: Erina Hamase, Masaaki Tanaka, Toshiki Ezure, Yasuhiro Miyake

المصدر: The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2023, :1877

3

Academic Journal

INVESTIGATION OF OPTIMIZATION PROCESS FOR CORE DESIGN WITH INTEGRATED ANALYSIS BETWEEN NEUTRONICS AND PLANT DYNAMICS

المؤلفون: Erina Hamase, Kazuki Kuwagaki, Kenji Yokoyama, Masaaki Tanaka, Norihiro Doda

المصدر: The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2023, :1153

4

Academic Journal

Development of Numerical Estimation Method for Thermal Hydraulics in Reactor Vessel of Sodium-cooled Fast Reactor under Decay Heat Removal Operation (Validation Practice with Decay Heat Removal Test) / ナトリウム冷却高速炉の崩壊熱除去システム運用時の原子炉容器内熱流動解析評価手法整備（崩壊熱除去試験を対象とした妥当性確認解析）

المؤلفون: Erina HAMASE, Masaaki TANAKA, Toshiki EZURE, Yasuhiro MIYAKE, 三宅康洋, 江連俊樹, 浜瀬枝里菜, 田中正暁

المصدر: The Proceedings of Conference of Kanto Branch. 2023, :17

5

Academic Journal

Core thermal-hydraulics analysis during dipped-type direct heat exchanger operation in natural circulation conditions

المؤلفون: Erina HAMASE, Yasuhiro MIYAKE, Yasutomo IMAI, Norihiro DODA, Ayako ONO, Masaaki TANAKA

المصدر: Mechanical Engineering Journal, Vol 9, Iss 4, Pp 21-00438-21-00438 (2022)

مصطلحات موضوعية: sodium-cooled fast reactor, core-plenum interactions, interwrapper flow, natural circulation, decay heat removal, subchannel, computational fluid dynamics, Mechanical engineering and machinery, TJ1-1570

وصف الملف: electronic resource

Relation: https://www.jstage.jst.go.jp/article/mej/9/4/9_21-00438/_pdf/-char/en; https://doaj.org/toc/2187-9745

URL الوصول: https://doaj.org/article/25583c7c56604d5199cb675a06a5a10c

View record in DOAJ

6

Academic Journal

Investigation of Core Deformation Reactivity Model Improvement in Plant Dynamics Analysis Code during ULOHS Test of U.S. Experimental Fast Reactor EBR-II / 米国高速実験炉EBR-IIでのULOHS模擬試験を対象としたプラント動特性解析コードの炉心変形反応度モデル高度化検討

المؤلفون: Erina HAMASE, Kazuo YOSHIMURA, Kennichi IGAWA, Masaaki TANAKA, Norihiro DODA, Tatsuya FUJISAKI, 井川健一, 吉村一夫, 堂田哲広, 浜瀬枝里菜, 田中正暁, 藤﨑竜也

المصدر: The Proceedings of the National Symposium on Power and Energy Systems. 2022, :231

7

Academic Journal

Benchmark Analysis of FFTF Unprotected Loss of Flow without Scram Test No.13 with Fast Reactor Plant Dynamics Analysis Code Super-COPD / 高速炉プラント動特性解析コードSuper-COPDによるFFTF LOFWOS No.13試験のベンチマーク解析

المؤلفون: Erina HAMASE, Hidemasa YAMANO, Kazuya OHGAMA, Masaaki TANAKA, Norihiro DODA, Takumi KAWAMURA, 堂田哲広, 大釜和也, 山野秀将, 河村拓己, 浜瀬枝里菜, 田中正暁

المصدر: The Proceedings of Mechanical Engineering Congress, Japan. 2021, :S081-01

8

Academic Journal

Preliminary analysis of sodium experimental apparatus PLANDTL-2 for development of evaluation method for thermal-hydraulics in reactor vessel of sodium fast reactor under decay heat removal system operation condition

المؤلفون: Ayako ONO, Masaaki TANAKA, Yasuhiro MIYAKE, Erina HAMASE, Toshiki EZURE

المصدر: Mechanical Engineering Journal, Vol 7, Iss 3, Pp 19-00546-19-00546 (2020)

مصطلحات موضوعية: sodium-cooled fast reactor, decay heat removal system, dipped-type direct heat exchanger, natural circulation, thermal-hydraulics in reactor vessel, numerical simulation, Mechanical engineering and machinery, TJ1-1570

وصف الملف: electronic resource

Relation: https://www.jstage.jst.go.jp/article/mej/7/3/7_19-00546/_pdf/-char/en; https://doaj.org/toc/2187-9745

URL الوصول: https://doaj.org/article/82e37c2ecfc6479795ae3d20a3b898d0

View record in DOAJ

9

Academic Journal

Development of Numerical Estimation Method for Thermal Hydraulics in Reactor Vessel of Sodium-cooled Fast Reactor under Decay Heat Removal System Operation Conditions (Investigation of Thermal Hydraulic Modeling in Gap between Fuel Subassemblies) / ナトリウム冷却高速炉の崩壊熱除去システム運用時の炉内熱流動解析評価手法整備（燃料集合体間ギャップ部の熱流動解析モデルの予備検討）

المؤلفون: Erina HAMASE, Masaaki TANAKA, Norihiro KIKUCHI, Satoshi MURAKAMI, Tatsuya FUJISAK, Yasutomo IMAI, 今井康友, 村上諭, 浜瀬枝里菜, 田中正暁, 菊地紀宏, 藤崎竜也

المصدر: The Proceedings of Ibaraki District Conference. 2020, :304

10

Academic Journal

Development of reactor vessel thermal hydraulic evaluation method under natural circulation decay heat removal conditions in sodium-cooled fast reactor -Application of subchannel based CFD analysis method to a fuel subassembly at low flow rate conditions- / ナトリウム冷却高速炉の自然循環崩壊熱除去時における炉容器内熱流動解析評価手法整備－低流量条件での燃料集合体単体に対するサブチャンネルCFD解析手法の適用－

المؤلفون: Erina HAMASE, Masaaki TANAKA, Norihiro DODA, Yasutomo IMAI, 今井康友, 堂田哲広, 浜瀬枝里菜, 田中正暁

المصدر: The Proceedings of Mechanical Engineering Congress, Japan. 2020, :08111

11

Academic Journal

Study on applicability of fast reactor plant dynamics analysis code to core thermal hydraulics under natural circulation decay heat removal conditions

المؤلفون: Erina HAMASE, Norihiro DODA, Kunihiko NABESHIMA, Ayako ONO, Hiroyuki OHSHIMA

المصدر: Nihon Kikai Gakkai ronbunshu, Vol 83, Iss 848, Pp 16-00431-16-00431 (2017)

مصطلحات موضوعية: sodium-cooled fast reactor, natural circulation decay heat removal, plant dynamics analysis code, whole core model, Mechanical engineering and machinery, TJ1-1570, Engineering machinery, tools, and implements, TA213-215

وصف الملف: electronic resource

Relation: https://www.jstage.jst.go.jp/article/transjsme/83/848/83_16-00431/_pdf/-char/en; https://doaj.org/toc/2187-9761

URL الوصول: https://doaj.org/article/e5244e675f364166b590936fa2d6827e

View record in DOAJ

12

Academic Journal

PRELIMINARY ANALYSIS OF SODIUM EXPERIMENTAL APPARATUS PLANDTL-2 FOR DEVELOPMENT OF EVALUATION METHOD FOR THERMAL HYDRAULICS IN REACTOR VESSEL OF SODIUM FAST REACTOR UNDER DECAY HEAT REMOVAL SYSTEM OPERATION CONDITION

المؤلفون: Ayako ONO, Erina HAMASE, Masaaki TANAKA, Toshiki Ezure, Yasuhiro MIYAKE

المصدر: The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2019, :2318

13

Academic Journal

Development of Numerical Estimation Method for Thermal Hydraulics in Reactor Vessel of Sodium-cooled Fast Reactor under Decay Heat Removal System Operation Conditions (Preliminary Thermal Hydraulics Simulation for Simulated Reactor Vessel in Sodium experimental apparatus PLANDTL-2) / ナトリウム冷却高速炉の崩壊熱除去システム運用時の炉内熱流動解析評価手法整備

المؤلفون: Ayako ONO, Erina HAMASE, Masaaki TANAKA, Toshiki EZURE, Yasuhiro MIYAKE, 三宅康洋, 小野綾子, 江連俊樹, 浜瀬枝里菜, 田中正暁

المصدر: The Proceedings of Ibaraki District Conference. 2018, :307

14

Academic Journal

Validation of plant dynamics analysis code for fast reactor core thermal hydraulics under natural circulation conditions / 高速炉自然循環時炉心内熱流動現象に対するプラント動特性解析コードの妥当性確認

المؤلفون: Ayako ONO, Erina HAMASE, Hiroyuki OHSHIMA, Kunihiko NABESHIMA, Norihiro DODA, 堂田哲広, 大島宏之, 小野綾子, 浜瀬枝里菜, 鍋島邦彦

المصدر: The Proceedings of the National Symposium on Power and Energy Systems. 2016, :244

15

Academic Journal

S083012 Current Status of Sodium Fire Analysis Code System Development and Validation / S083012 ナトリウム燃焼影響解析評価手法の開発研究([S083-01]原子力システムおよび要素技術)

المؤلفون: Erina HAMASE, Shuji OHNO, 大野修司, 浜瀬枝里菜

المصدر: The Proceedings of Mechanical Engineering Congress, Japan. 2013, 1

16

Academic Journal

Denaturing of Pu in Fast Breeder Reactor / 高速増殖炉におけるPuの改質に関する研究

المؤلفون: Erina HAMASE, Hiroshi SAGARA, Masaki SAITO, 浜瀬枝里菜, 相楽洋, 齊藤正樹

المصدر: Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan. 2009, :241

17

Academic Journal

Verification and Validation of Sodium Fire Analysis Codes for Fast Reactors (5) Evaluation of Multi-Dimensional Analysis Effectiveness with AQUA-SF / ナトリウム燃焼解析コードの検証・整備

المؤلفون: Erina Hamase, Hideki Kamide, Hiroshi Ohki, Shuji Ohno, 上出英樹, 大木裕, 大野修司, 浜瀬枝里菜

المصدر: Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan. 2013, :230

18

Academic Journal

Verification and Validation of Sodium Fire Analysis Codes for Fast Reactors (4) Analysis of Combustion Test with Large Sodium Leakage Rate in 2 Cells Geometry / ナトリウム燃焼解析コードの検証・整備

المؤلفون: ERINA HAMASE, SHUJI OHNO, 大野修司, 浜瀬枝里菜

المصدر: Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan. 2013, :229

19

Academic Journal

Verification and Validation of Sodium Fire Analysis Codes for Fast Reactors (3)Assessment of Dominant Factors by Sensitivity Analyses / ナトリウム燃焼解析コードの検証・整備

المؤلفون: Erina Hamase, Hideki Kamide, Shuji Ohno, 上出英樹, 大野修司, 浜瀬枝里菜

المصدر: Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan. 2012, :266

20

Academic Journal

MA添加による内部ブランケットを有する高速増殖炉の長寿命化の研究 / Study on long-life FBR with inner blanket by doping MA

المؤلفون: Erina HAMASE, Hiroshi SAGARA, Masaki SAITO, 浜瀬枝里菜, 相楽洋, 齊藤正樹

المصدر: Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan. 2010, :263

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