Flow and temperature distribution evaluation on sodium heated large-sized straight double-wall-tube steam generator

Kisohara, Naoyuki; Moribe, Takeshi; Sakai, Takaaki

Proceedings of 2006 International Congress on Advances in Nuclear Power Plants (ICAPP '06) (CD-ROM), 9 Pages, 2006/06

The sodium heated steam generator (SG) of the commercialized FBR being designed in the Feasibility Study is a straight double-wall-tube type and it is large-sized to reduce the manufacturing cost by economics of scale. This paper addresses the temperature and flow multi-dimensional distributions at steady state to obtain the prospect of the SG. Large-sized heat exchanger components are prone to have non-uniform flow and temperature distributions. These phenomena might lead to tube buckling or tube to tube-sheet junction failure in straight tube type SGs. The flow adjustment devices installed in the SG are optimized to prevent these issues, and the temperature distribution properties are uncovered by analysis methods. The analysis model of the SG consists of two parts, a sodium inlet distribution plenum (the plenum) and a heat transfer tubes bundle region (the bundle). The flow and temperature distributions in the plenum and the bundle are evaluated by the three-dimensional flow code "FLUENT" and the two dimensional thermal-hydraulic code "MSG". The MSG code is particularly developed for sodium heated SGs in JAEA. These codes have revealed that the sodium flow is distributed uniformly by the flow adjustment devices, and that the lateral tube temperature distributions remain within the allowable temperature range for the structural integrity of the tubes and the tube to tube-sheet junction.

Study on plant concept for Gas Cooled Fast Reactor

Moribe, Takeshi; Kubo, Shigenobu; Saigusa, Toshiie; Konomura, Mamoru

JNC TY9400 2004-007, 408 Pages, 2004/06

JNC-TY9400-2004-007.pdf:26.6MB

In "Feasibility Study on Commercialized Fast Reactor Cycle System", technological options including various coolant (sodium, heavy metal, gas, water, etc.), fuel type (MOX, metal, nitride) and output power are considered and classified, and commercialized FBR that have economical cost equal to LWR are pursued. In FY2003, in order to define the prospect for technical feasibility of the helium gas cooled FR using coated particle fuel (He GFR), which has been selected as a prospective concept in FY2001, the preliminary conceptual designs of the core and plant are conducted, and a concept of gas cooled plant is established and data required for the interim evaluation of Phase 2 are prepared. This report summarizes the results of the plant design study and the preparation of data for "Multi-Criteria Evaluation" in FY2003. The result of study: (1)The plant specifications and main equipment concept design were studied for preliminary plant design. In this study, effectiveness of the thermal insulators in the reactor structure, seismic evaluation of the gas turbines and integrity of structure in the core catcher were studied. The plant layout was reviewed based on the results of plant designs. (2)The result of study for the preparation of data for "Multi-Criteria Evaluation" : ISI procedure (draft) for the primary system equipment of He GFR was set up, and the inspection processes were reviewed, according to the ISI standard for LWR. The amount of wastes produced in decommissioning and operation was roughly estimated.Major R&D items concerning the He GFR plant design were proposed including the required methods and schedules. (3)The data required for construction cost evaluation was prepared, and the construction cost of He GCR was 10% above the target cost.

Study on plant concept for gas cooled fast reactor

Moribe, Takeshi; Kubo, Shigenobu; Saigusa, Toshiie; Konomura, Mamoru

JNC TY9400 2003-007, 188 Pages, 2003/05

JNC-TY9400-2003-007.pdf:7.62MB

In (Feasibility Study on Commercialized Fast Reactor Cycle System), technological options including various coolant (sodium,heavy metal, gas, water,etc.), fuel type (MOX, metal, nitride) and output power are considered and classified, and commercialized FBR that have economical cost equal to LWR are pursued. In conceptual study on gas cooled FBR in FY2002, to identify the prospect of the technical materialization of the helium cooled FBR using coated particle fuel which is an attractive concept extracted in the year of FY2001, the preliminary conceptual design of the core and entire plant was performed. This report summarizes the results of the plant design study in FY2002. The result of study is as follows. (1)For the passive core shutdown equipment, the curie point magnet type self-actuated device was selected and the device concept was set up. (2)For the reactor block, the concept of the core supporting structure, insulators and liners was set up. For the material of the heat resistant structure, SiC was selected as a candidate. (3)For the seismic design of the plant, it was identified that a design concept with three-dimensional base isolation could be feasible taking the severe seismic condition into account. (4)For the core catcher, an estimation of possible event sequences under severe core damage condition was made. A core catcher concept which may suit the estimation was proposed. (5)The construction cost was roughly estimated based on the amount of materials and its dependency on the plant output power was evaluated. The value for a small sized plant exceeds the target construction cost about 20%.

Design study of double wall straight tube steam generator (SG), 3; Evaluation of thermo hydraulic analysis

Moribe, Takeshi; Sakai, Takaaki; Ikeda, Hirotsugu*; Yamada, Yumi*; Kurome, Kazuya*

no journal, , 

no abstracts in English