Installation of the water environment irradiation facility for the IASCC research under the BWR irradiation environment, 1

Okada, Yuji; Magome, Hirokatsu; Hanawa, Hiroshi; Omi, Masao; Kanno, Masaru; Iida, Kazuhiro; Ando, Hitoshi; Shibata, Mitsunobu; Yonekawa, Akihisa; Ueda, Haruyasu

JAEA-Technology 2013-019, 236 Pages, 2013/10

JAEA-Technology-2013-019.pdf:45.07MB

In Japan Atomic Energy Agency, in order to solve the problem in the long-term operation of a light water reactor, preparation which does the irradiation experiment of light-water reactor fuel and material is advanced. JMTR stopped after the 165th operation cycle in August 2006, and is advancing renewal of the irradiation facility towards re-operation. This material irradiation test facility and power ramping test facility for doing the neutron irradiation test of the fuel and material for light water reactors is scheduled to be manufactured and installed between the 2008 fiscal year and the 2012 fiscal year. This report summarizes manufacture and installation of the material irradiation test facility for IASCC research carried out from the 2008 fiscal year to the 2010 fiscal year.

Development of CAD-to-MCNP model conversion system and its application to ITER

Sato, Satoshi; Iida, Hiromasa; Ochiai, Kentaro; Konno, Chikara; Nishitani, Takeo; Morota, Hidetsugu*; Nashif, H.*; Yamada, Masao*; Masuda, Fukuzo*; Tamamizu, Shigeyuki*; et al.

Nuclear Technology, 168(3), p.843 - 847, 2009/12

https://doi.org/10.13182/NT09-A9316

It takes huge or unrealistic amounts of time to prepare accurate calculation inputs in shielding design for very large and complicated structure such as fusion reactors. For that reason, we have developed an automatic conversion system from three dimensional CAD drawing data into input data of the calculation geometry for a three dimensional Monte Carlo radiation transport calculation code MCNP, and applied it to an ITER benchmark model. This system consists of a void creation program (CrtVoid) for CAD drawing data and a conversion program (GEOMIT) from CAD drawing data to MCNP input data. CrtVoid creates void region data by subtracting solid region data from the whole region by Boolean operation. The void region data is very large and complicated geometry. The program divides the overall region to many small cubes, and the void region data can be created in each cube. GEOMIT generates surface data for MCNP data based on the CAD data with voids. These surface data are connected, and cell data for MCNP input data are generated. In generating cell data, additional surfaces are automatically created in the program, and undefined space and duplicate cells are removed. We applied this system to the ITER benchmark model. We successfully created void region data, and MCNP input data. We calculated neutron flux and nuclear heating. The calculation results agreed well with those with MCNP inputs generated from the same CAD data with other methods.

Mechanistic approach to the sodium leakage and fire analysis

Yamaguchi, Akira; Muramatsu, Toshiharu; Ohira, Hiroaki; Iida, Masao

PNC TN9410 97-040, 141 Pages, 1997/04

PNC-TN9410-97-040.pdf:7.71MB

In December 1995, a thermocouple well was broken and liquid sodium leaked out of the intermediate heat transport system of the prototype fast breeder reactor Monju. In the initiating process of the incident, liquid sodium flowed out through the hollow thermocouple well, nipple and connector. As a result, liquid sodium, following ignition and combustion, was dropping from the connector to colide with the duct and gating placed below. The collision may cause fragmentation and scattering of the sodium droplet that finaly was piled up on the floor. This report deals with the development of computer programs for the phenomena based on mechanistics approach. Numerical analyses are also made for fundamental sodium leakage and combustion phenomenon, sodium combustion experiment, and Monju incident condition. The contents of this report is listed below: (1)Analysis of chemical reaction process based on molecular orbital method, (2)Thermal hydlaulic analysis of the sodium combustion experiment II performed in 1996 at O-arai Engineering Center, PNC, (3)Thermal hydlaulic analysis of room A-446 of Monju reactor when the sodium leakage took place, (4)Direct numerical simulation of sodium droplet, (5)Sodium leakage and scattering analysis using three dimensional particle method, (6)Multi-dimensional combustion analysis and multi-point approximation combustion analysis code. Subsequent to the development work of the programs, they are to be applied to the safety analysis of the Fast Breeder Reactor.

Improvement of free surface tracing for fluid dynamic analysis code:SPLASH-ALE

Iida, Masao

PNC TN9410 96-110, 30 Pages, 1996/04

PNC-TN9410-96-110.pdf:5.48MB

SPLASH-ALE is a three dimensional finite element hydrodynamic code employing Arbitrary-Lagrangian-Eulerian method which enables computational nodes to move in arbitrary velocity. To avoid an abnormal termination of calculation caused by extreme deformation of element, a node mobility scheme, horizontally Eulerian and vertically uniformed, is available for calculating flow in tank, which have inlet, outlet and free surface, such as a FBR reactor vessel. Author improved the evaluation method for the free surface tracing to consider free surface movement in horizontal direction in which node coordinate is fixed for this node mobility scheme. To cvaluate the improvement, a surface swell formation caused by an upward plane jet impinging on free surface was calculated, Thus it was confirmed that free surface representation was enhanced and that error of flow rate at free surface was significantly reduced.

2nd power-up test for JRR-2

Kambara, Toyozo; Uno, Hidero; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Kohayakawa, Toru; Takayanagi, Hiroshi; Fujimura, Tsutomu; Morita, Morito; Ichihara, Masahiro; et al.

JAERI 1045, 11 Pages, 1963/03

JAERI-1045.pdf:0.72MB

no abstracts in English

Development of the CAD/MCNP automatic conversion code, GEOMIT, 1; CAD pre-processing tool, Development of the CrtVoid

Morota, Hidetsugu*; Yamada, Masao*; Nasif, H.*; Masuda, Fukuzo*; Iida, Hiromasa; Sato, Satoshi; Nishitani, Takeo; Tamamizu, Shigeyuki*; Karaki, Junichi*

no journal, , 

Development of CAD preprocessing tool "CrtVoid" is reported. The code extracts surface element information and re-arrange them as input data for CAD/MCNP automatic conversion cord "GEOMIT". Reports includes detail of the development and test results of confirmation of its functions.