Refine your search:     
Report No.
 - 
Search Results: Records 1-5 displayed on this page of 5
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

JAEA Reports

Evaluation of neutronic characteristics of TRACY water-reflected core system

Sono, Hiroki; Yanagisawa, Hiroshi*; Miyoshi, Yoshinori

JAERI-Tech 2003-096, 84 Pages, 2004/01

JAERI-Tech-2003-096.pdf:3.6MB

Prior to the supercritical experiments using a water-reflected core of the TRACY Facility, neutronic characteristics regarding criticality and reactivity of the core system were evaluated. In the analyses, a continuous energy Monte Carlo code, MVP, and a two-dimensional transport code, TWOTRAN, were used together with a nuclear data library, JENDL-3.3. By comparison to the characteristics in the former-used bare core system of TRACY, the water reflector was estimated not to change the kinetic parameter and to reduce the critical solution level by $$sim$$20 %, the temperature coefficient of reactivity by 6$$sim$$10 %, and the void coefficient of reactivity by $$sim$$18 %, respectively. According to the Nordheim-Fuchs model, the first peak power during a power excursion was evaluated to be $$sim$$15 % smaller than that in the bare system under the same conditions of fuel and reactivity insertion. The influence of the void feedback effect of reactivity, which is left out of consideration in the model, on the power characteristics will be evaluated from the results of the experiments.

Journal Articles

Nuclear characteristics evaluation for a supercritical experiment facility using low-enriched uranium solution fuel, TRACY

Nakajima, Ken

Proceedings of International Conference on the New Frontiers of Nuclear Technology; Reactor Physics, Safety and High-Performance Computing (PHYSOR 2002) (CD-ROM), 8 Pages, 2002/10

The nuclear characteristics of TRACY, such as the criticality, the $$beta$$$$_{eff}$$/$$Lambda$$ ratio, the peak power, the energy of pulse, and the total energy, have been evaluated using the experimental data. TRACY is a supercritical reactor fueled with low-enriched uranyl nitrate aqueous solution to simulate criticality accidents in a fuel processing facility, such as a spent-fuel reprocessing plant. In this evaluation, the availability of criticality calculation and the models to evaluate the power and energy have been studied.

Journal Articles

Study on reactivity feedback effects in the TRACY transient experiments

Nakajima, Ken; ;

Proceedings of 6th International Conference on Nuclear Criticality Safety (ICNC '99), 3, p.1286 - 1292, 1999/00

no abstracts in English

Journal Articles

Experimental study on criticality accidents using the TRACY

Nakajima, Ken; ; ; ; ; Sakuraba, Koichi; Ono, Akio

PHYSOR 96: Int. Conf. on the Physics of Reactors, 4, p.L83 - L92, 1996/00

no abstracts in English

Journal Articles

Cryogenic system design and its component development for Fusion Experimental Reactor(FER)

Kato, Takashi; Tada, Eisuke; Hiyama, Tadao; Kawano, Katsumi; ; ; ; ; Shimamoto, Susumi

Fusion Technology 1990, p.1535 - 1539, 1991/00

no abstracts in English

5 (Records 1-5 displayed on this page)
  • 1