Study on loss-of-cooling and loss-of-coolant accidents in spent fuel pool, 1; Overview

Kaji, Yoshiyuki; Nemoto, Yoshiyuki; Nagatake, Taku; Yoshida, Hiroyuki; Tojo, Masayuki*; Goto, Daisuke*; Nishimura, Satoshi*; Suzuki, Hiroaki*; Yamato, Masaaki*; Watanabe, Satoshi*

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 8 Pages, 2019/05

https://doi.org/10.1299/jsmeicone.2019.27.1343

In this research program, cladding oxidation model in SFP accident condition, and numerical simulation method to evaluate capability of spray cooling system which was deployed for spent fuel cooling during SFP accident, have been developed. These were introduced into the severe accident codes such as MAAP and SAMPSON, and SFP accident analyses were conducted. Analyses using Computational Fluid Dynamics (CFD) code were conducted as well for the comparison with SA code analyses and investigation of detail in the SFP accident. In addition, three-dimensional criticality analysis method was developed as well, and safer loading pattern of spent fuels in pool was investigated.

Feasibility study for fast reactor and related fuel cycle; Preliminary studies in 1998

Hayafune, Hiroki; ; ; ; ; ;

JNC TN9420 99-004, 195 Pages, 1999/06

JNC-TN9420-99-004.pdf:15.24MB

Prior to the feasibility study for fast reactors (FRs) starting from the 1999 fiscal year, planned in the medium and long-term program of JNC, preliminarily studies were performed on "Large FRs (Sodium cooled and MOX fueled) with innovative technologies as a Standard Plant" and "FR systems except sodium cooled, MOX fueled reactors". (1)Standard plant. The following concepts were created in respect of an economic goal for the commercialization. (a)The concepts of reactor and cooling systems: 18 cases (4 cases indude secondary system deletion concept) (b)The concepts of upper core structure and fuel handling systems: 4 cases (example: Fuel handling system) (c)The concepts of FR and fuel recycle co-location systems: 5 cases (2)FR systems except standard plant. Gas cooled reactors, heavy metal (Pb or Pb-Bi) cooled reactors and small scale or module type reactors were studied on the basis of literature. They were evaluated from the viewpoint of the technical possibility (the structure integrity, earthquake resistance, safety, productivity, operability, maintenance repair, difficulty of the development), the long-term targets (market competitiveness as an energy system, utilization of uranium resources, reduction of radioactive waste, security of the non-proliferation), and developmental risk. As the result, the following concepts should be studied for future commercialized FRs. (a)Small scale and module type feactor: Middle-sized reactor with an excellent economical efficiency. Small power feactor with a multipurpose design concept. (b)Gas cooled reactor: CO gas cooled reactor, He gas cooled reactor (c)Heavy metal cooled reactor: Russian type lead cooled reactor (d)Light water cooled reactor: RBWR and super critical pressure light water cooled reactor (e)Molten salt reactor: Trichloride molten salt reactor which matches ...

Study on improvement of safety for accident conditions in spent fuel pool, 20; Overview

Kaji, Yoshiyuki; Nemoto, Yoshiyuki; Nagatake, Taku; Yoshida, Hiroyuki; Tojo, Masayuki*; Goto, Daisuke*; Nishimura, Satoshi*; Suzuki, Hiroaki*; Yamato, Masaaki*

no journal, , 

The objectives of this study is to enhance the analytical method and safety of spent fuel pool under severe accident conditions. In this presentation, we explain about general view of results of this project.