A Recent experimental program to evidence in-vessel retention by controlled material relocation during core disruptive accidents of sodium-cooled fast reactors

Matsuba, Kenichi; Kamiyama, Kenji; Toyooka, Junichi; Zuev, V. A.*; Ganovichev, D. A.*; Kolodeshnikov, A. A.*

Proceedings of 10th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-10) (USB Flash Drive), 5 Pages, 2016/11

Molten fuel discharge through control rod guide tubes (CRGTs) is a key process that dominates the termination of core disruptive accidents of sodium-cooled fast reactors, since fuel dispersion from the core contributes to the achievement of both deeper subcriticality in the degraded core and formation of coolable debris bed. Within a framework of a collaborative research program between Japan Atomic Energy Agency and National Nuclear Center of the Republic of Kazakhstan, called EAGLE program, a new experimental program has been started with out-of-pile experiments to clarify the fuel discharge through CRGTs. This paper presents the status of the new program, including experimental results obtained so far.

Shielding analysis of neutron detector guide tubes of advanced marine reactor MRX

*; Ishida, Toshihisa; *

JAERI-Tech 98-030, 38 Pages, 1998/08

JAERI-Tech-98-030.pdf:1.73MB

no abstracts in English

Operational test (II) of falled fuel detection and location system (FFDL) of Joyo

Morimoto, Makoto; Okubo, Toshiyuki; ; ; ; ;

PNC TN9410 91-334, 64 Pages, 1991/10

PNC-TN9410-91-334.pdf:1.72MB

An failed fuel detection and location system (FFDL) using a sipping method is adopted as the FFDL of Joyo. FFDL has not operated since the first falled fuel simulated (FFDL-I) test in April, 1985 because Joyo has not yet experienced any operation with breached fuels. Therefore, the operational test (II) of FFDL was carried out on July 1219, 1991 for a preparation of the FFDL-II test which is scheduled in 1992. Main results from the test are as follows ; (1)The adequacy of the functions and operating procedure of FFDL was reaffirmed and the operating experience was gained. (2)Radioactivity measurement was conducted by FFDL for six subassemblies and their integrity was confirmed.

Study on the discharge behavior of molten core materials through the control rod guide tube in the core disruptive accident of SFR

Kato, Shinya; Matsuba, Kenichi; Kamiyama, Kenji; Zuev, V.*; Ganovichev, D.*; Baklanov, V.*

no journal, , 

To clarify the molten material outflow behavior from the reactor core region through the control rod guide tube(CRGT) in the core disruptive accident of SFR, the out-of-pile tests simulating the molten material dropping into the CRGT, they are imitated by the molten alumina and the stainless cup respectively, were conducted. In this presentation, the evaluation result of the tests will be reported.