Validation of the Hybrid Turbulence Model in Detailed Thermal-Hydraulic Analysis Code SPIRAL for Fuel Assembly Using Sodium Experiments Data of 37-Pin Bundles-Reference-Cited by-同舟云学术

Validation of the Hybrid Turbulence Model in Detailed Thermal-Hydraulic Analysis Code SPIRAL for Fuel Assembly Using Sodium Experiments Data of 37-Pin Bundles

Published:2023-10-05 Issue: Volume: Page:1-22
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Yoshikawa Ryuji¹^ORCID,Imai Yasutomo²,Kikuchi Norihiro¹,Tanaka Masaaki¹^ORCID,Ohshima Hiroyuki¹

Affiliation:

1. Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Ibaraki 311-1393, Japan

2. NDD Corporation, 1-1-6 Jonan, Mito, Ibaraki 310-0803, Japan

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295450.2023.2249707

Reference20 articles.

1. A NEXT GENERATION SODIUM-COOLED FAST REACTOR CONCEPT AND ITS R&D PROGRAM

2. H. OHSHIMA and Y. IMAI, “Development of Analysis Program for Detailed Thermal Hydraulics in Fast Reactor Fuel Assembly (4) Incorporation of Energy Equation Solver with Turbulence Model,” Proc. Autumn 2003 Annual Mtg. of Atomic Energy Society of Japan, Shizuoka, Japan, September 24–26, 2003, p. 354, F1, Atomic Energy Society of Japan (2003) (in Japanese).

3. H. OHSHIMA and Y. IMAI, “Numerical Simulation of Flow Field in Wire-Wrapped Fuel Pin Bundle of Sodium Cooled Fast Reactor Using ‘SPIRAL,’” Proc. Fifth Korea-Japan Symp. Nuclear Thermal Hydraulics and Safety, NTHAS5-F011, Jeju, Korea, November 26–29, 2006.

4. H. OHSHIMA and Y. IMAI, “Numerical Simulation Method of Thermal-Hydraulics in Wire-Wrapped Fuel Pin Bundle of Sodium-Cooled Fast Reactor,” Proc. Int. Conf. Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development, IAEA-CN245-453, Yekaterinburg, Russian Federation, June 26–29, 2017.

5. H. OHSHIMA and Y. IMAI, “Development of Thermal Hydraulic Analysis Program for Wire-Wrapped Fuel Pin Bundle of Fast Reactor,” Proc. JSME Annual Mtg., p. 153, Nagoya, Japan, September 5–8, 2010, The Japan Society of Mechanical Engineers (2010) (in Japanese).