次世代高速炉の核設計における燃焼核特性評価の解析条件の検討

Material type: 文書・図像類

Author: 滝野一夫ほか

Publisher: -

Publication date: 2023-05

Material Format: Digital

Capacity, size, etc.: -

NDC: -

View All

Notes on use

Note (General)：: Since next-generation fast reactors aim to achieve a higher core discharge burn-up than conventional reactors do, core neutronics design methods must ...

Detailed bibliographic record

Summary, etc.：: Since next-generation fast reactors aim to achieve a higher core discharge burn-up than conventional reactors do, core neutronics design methods must ...

Search by Bookstore

Holdings of Libraries in Japan

This page shows libraries in Japan other than the National Diet Library that hold the material.

List of Cooperating Institutions and Databases

Please contact your local library for information on how to use materials or whether it is possible to request materials from the holding libraries.

other

JOPSS:JAEA Originated Papers Searching System
Digital
You can check the holdings of institutions and databases with which Institutional Repositories DataBase(IRDB)(Institutional Repository) is linked at the site of Institutional Repositories DataBase(IRDB)(Institutional Repository).
JOPSS:JAEA Originated Papers Searching System

Search by Bookstore

Bibliographic Record

You can check the details of this material, its authority (keywords that refer to materials on the same subject, author's name, etc.), etc.

Digital

Material Type: 文書・図像類
Title: 次世代高速炉の核設計における燃焼核特性評価の解析条件の検討
Author/Editor: 滝野一夫
大木繁夫
Author Heading: 滝野一夫
大木繁夫
Publication Date: 2023-05
Publication Date (W3CDTF): 2023-05
Alternative Title: Investigation of the core neutronics analysis conditions for evaluation of burn-up nuclear characteristics of the next-generation fast reactors
Periodical title: JAEA-Data/Code 2023-003
Text Language Code: eng
Target Audience: 一般
Note (General): Since next-generation fast reactors aim to achieve a higher core discharge burn-up than conventional reactors do, core neutronics design methods must be refined. Therefore, a suitable analysis condition is required for the analysis of burn-up nuclear characteristics to accomplish sufficient estimation accuracy while maintaining a low computational cost. We investigated the effect of the analysis conditions on the accuracy of estimation of the burn-up nuclear characteristics of next-generation fast reactors in terms of neutron energy groups, neutron transport theory, and spatial mesh. This study treated the following burn-up nuclear characteristics: criticality, burn-up reactivity, control rod worth, breeding ratio, assembly-wise power distribution, maximum linear heat rate, sodium void reactivity, and Doppler coefficient for the equilibrium operation cycle. As a result, it was found that the following conditions were the most suitable: 18-energy-group structure, 6 spatial meshes per assembly with diffusion approximation. Additionally, these conditions should apply to correction factors for energy group structure, spatial mesh and transport effects.
次世代高速炉は、従来炉よりも高い炉心取出燃焼度を目指しているため、炉心核設計の高度化が求められる。そのため、燃焼核特性解析では、計算コストを抑えつつ十分な計算精度が得られる適切な解析条件が必要とされる。そこで、次世代高速炉の燃焼核特性の計算精度に及ぼす解析条件の影響を、中性子エネルギー群、中性子輸送理論、空間メッシュに着目して調査した。本検討では燃焼核特性として、平衡サイクルにおける臨界性、燃焼反応度、制御棒価値、増殖比、集合体単位の出力分布、最大線出力、ナトリウムボイド反応度、ドップラー係数を取り扱った。検討の結果、エネルギー群を18群とし、拡散近似を用いて1集合体あたり6メッシュ分割して、エネルギー群、空間メッシュ、輸送効果の補正係数を適用することが最適であることが分かった。
Source: /JAEA-Data-Code-2023-003.pdf （fulltext）
https://jopss.jaea.go.jp/pdfdata/JAEA-Data-Code-2023-003.pdf
Access Restrictions: 限定公開
Data Provider (Database): 国立情報学研究所 : 学術機関リポジトリデータベース（IRDB）（機関リポジトリ）
https://irdb.nii.ac.jp
Original Data Provider (Database): 日本原子力研究開発機構 : JOPSS:JAEA Originated Papers Searching System