Conceptual Reactor Design Study of Very High Temperature Reactor (VHTR) with Prismatic-Type Core

Author:

NAKANO Masaaki1,TSUJI Nobumasa1,TAZAWA Yujiro1

Affiliation:

1. Fuji Electric Advanced Technology Co., Ltd.

Publisher

Japan Society of Mechanical Engineers

Reference6 articles.

1. (1) Nojiri, N., Fujimoto, N., Mouri, T. and Obata, H., DELIGHT-8; One Dimensional Fuel Cell Burnup Analysis Code for High Temperature Gas-cooled Reactors (HTGR), JAERI-Data/Code 2004-012, (2004), (in Japanese)

2. (2) Fowler, T. B., Vondy, D. R., and Cummingham, G. W., Nuclear Reactor Core Analysis Code: CITATION, ORNL-TM-2496 Rev. 2

3. (3) Maruyama, S., Murakami, T., Kiso, Y. and Sudo, Y., Verification of in-vessel thermal and hydraulic analysis code FLOWNET, JAERI-M 88-138, (in Japanese)

4. (4) Peterson, J., TAC2D A General Purpose Two-dimensional Heat Transfer Computer Code-User's Manual-, GA-8868 (1969)

5. (5) K. Sawa, F. Okamoto, K. Sasaki, S. Shiozawa, Analysis Method of Fractional Release of Cesium from Fuel Elements of HTTR, JAERI-M 90-063, (in Japanese)

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