Core design study on rock-like oxide fuel light water reactor and improvements of core characteristics
Bibliographic record
Abstract
No abstract is available for this record. The assistant can identify its topic from the title, but cannot infer the study’s results.
Source: Not provided · Quality: missing
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Nuclear materials and radiation effects
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (10)
Show source-provided references
1. H. Akie, H. Takano, Y. Anoda, T. Muromura, Plutonium annihilation in rock-like fuel LWR, in: Proceedings of the 10th Pacific Basin Nuclear Conference (10-PBNC), vol.2, Kobe, Japan, 20–25 October 1996, p. 1183
2. H. Akie, H. Takano, Y. Anoda, T. Muromura, Conceptual core design study of plutonium rock-like oxide fuel PWR, in: Proceedings of the International Conference on Future Nuclear Systems (Global'97), vol.2, Yokohama, Japan, 5–10 October 1997, p. 1136
3. N. Nitani, T. Yamashita, T. Ohmichi, T. Muromura, Phase relations and thermophysical properties of plutonium rock-like fuels for LWR use, in: Proceedings of the 10th Pacific Basin Nuclear Conference (10-PBNC), vol. 2, Kobe, Japan, 20–25 October 1996, p. 1114
4. K. Okumura, K. Kaneko, K. Tsuchihashi, SRAC95; General purpose neutronics code system, Japan Atomic Energy Research Institute Report JAERI-Data/Code 96-015, 1996 (in Japanese)
5. T. Matsuda, S. Kobayashi, N. Nitani, T. Yamashita, T. Ohmichi, T. Muromura, Thermal expansion and thermal conductivity of rock-like fuel, Japan Atomic Energy Research Institute Report JAERI-Research 97-083, 1997 (in Japanese)
6. D.L. Hagrman, MATPRO-Version11, A Handbook of materials properties for use in the analysis of light water reactor fuel rod behavior, Idaho National Eng. Lab., 1981
7. N. Ohnishi, T. Harami, H. Hirose, M. Uemura, EUREKA-2: A computer code for the reactivity accident analysis in a water cooled reactor, Japan Atomic Energy Research Institute Report JAERI-M 84-074, 1984 (in Japanese)
8. K. Okonogi, T. Nakamura, M. Yoshinaga, K. Ishijima, H. Akie and H. Takano, these Proceedings, p. 167
9. C.E. Peterson, J.H. McFadden, M.P. Paulsen, G.C. Gose, RETRAN-02 – A program for transient thermal-hydraulic analysis of complex fluid flow systems, Electric Power Research Institute Report EPRI NP-1850 CCM, 1, 1981
10. T. Mori, M. Nakagawa, S. Fujii, Parametric study on thermal-hydraulic characteristics of high conversion light water reactor, Japan Atomic Energy Research Institute Report JAERI-M 88-224, 1988, pp. 93–147 (in Japanese)