Development of capsule design support subprograms for 3-dimensional temperature calculation using FEM code NISA

Tobita, Masahiro*; Matsui, Yoshinori

JAERI-Tech 2003-042, 132 Pages, 2003/03

JAERI-Tech-2003-042.pdf:7.19MB

Prediction of irradiation temperature is one of the important issues in the design of the capsule for irradiation test. Many kinds of capsules with complex structure have been designed for recent irradiation requests, and three-dimensional (3D) temperature calculation becomes inevitable for the evaluation of irradiation temperature. For such 3D calculation, however, many works are usually needed for input data preparation, and a lot of time and resources are necessary for parametric studies in the design. To improve such situation, JAERI introduced 3D-FEM (finite element method) code NISA (Numerically Integrated elements for System Analysis) and developed several subprograms, which enabled to support input preparation works in the capsule design. The 3D temperature calculation of the capsule are able to carried out in much easier way by the help of the subprograms, and specific features in the irradiation tests such as non-uniform gamma heating in the capsule, becomes to be considered.

Development of 3-dimensional capsule temperature calculation program using FEM (NISA Code)

Tobita, Masahiro*; Matsui, Yoshinori

KAERI/GP-195/2002, p.87 - 95, 2002/00

In the Japan Materials Testing Reactor (JMTR) of Japan Atomic Energy Research Institute (JAERI), the temperature distribution inside of irradiation specimens and capsules structure material are evaluated in the design of irradiation capsules. For the evaluation of detailed temperature distribution, NISA (Numerically Integrated elements for System Analysis) code has been introduced, and subprograms are developed to simplify the input data of the capsules structure and the analysis conditions using the three-dimensional finite element method. By the development of subprograms, prediction of the temperature distribution inside of irradiation specimens and capsules structure material became detailed and more accurate than calculation by one-dimensional code. Also estimation of detail temperature distribution during irradiation became possible based on the indication of thermocouple.

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

Evaluation of Fuel Centerline Temperature of LWR Fuel Rods During Fast Rise to Operating Power - Results from Halden Power Ramp Test

;

JAERI-M 82-127, 53 Pages, 1982/09

JAERI-M-82-127.pdf:1.49MB

no abstracts in English

Analysis of Pellet Center Temperature Measurements for HALDEN IFT-224 Using Program FREG-3

;

JAERI-M 6878, 29 Pages, 1977/01

JAERI-M-6878.pdf:0.78MB

no abstracts in English