Operating experience with the multienrichment initial core of the boiling water reactor Kashiwazaki-Kariwa Unit 5

Nuclear Technology

Volumn 114, Issue 3, 1996, Pages 308-316

  Mochida, Takaaki ^a,c,d   Nakamura, Mitsunari ^a,e   Yamashita, Jun Ichi ^a,f,g   Maruyama, Hiromi ^a,h   Muto, Sakae ^b   Kasai, Shigeru ^b  

^a HITACHI LTD   (Japan)

^b TOKYO ELECTRIC POWER COMPANY   (Japan)

^c TOKYO INSTITUTE OF TECHNOLOGY   (Japan)

^d UNIVERSITY OF MICHIGAN   (United States)

^e TOHOKU UNIVERSITY   (Japan)

^f HOKKAIDO UNIVERSITY   (Japan)

^g UNIVERSITY OF TOKYO   (Japan)

^h SHINSHU UNIVERSITY   (Japan)

Author keywords

Boiling water reactor core design; Initial core; Uranium utilization

Indexed keywords

BOILING WATER REACTORS; CONTROL RODS; NUCLEAR FUELS; TEMPERATURE MEASUREMENT; URANIUM;

CAPACITY FACTORS; FUEL DISCHARGE EXPOSURE; INITIAL CRITICALITY TEST; OPERABILITY; REACTOR CORE DESIGN;

REACTOR CORES;

EID: 0030168911     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/nt96-a35235     Document Type: Article

References (11)

1. T. SHIMOSHIGE, J. YAMASHITA, and N. TABATA, "Operating Experience with Axially Two-Zoned Initial Fuel Core," Trans. Am. Nucl. Soc., 50, 565 (1985).
2. A. NISHIMURA, M. YOKOMI, and A. YAMADA, "Experience with Single Control Rod Pattern Operation in Axially Two-Zoned Fuel Cores," Trans. Am. Nucl. Soc., 50, 567 (1985).
3. T. MOCHIDA, Y. MASUHARA, K. KANDA, Y. OKA, M. SASAKI, and S. SAKURAI, "Effective Utilization of Uranium and Plutonium in LWR Cores - Uranium Utilization Improvements," Trans. Am. Nucl. Soc., 66, 460 (1992).
4. S. R. SPECKER, L. E. FENNERN, R. E. BROWN, K. L. STARK, and R. L. CROWTHER, "The BWR Control Cell Core Improved Design," Trans. Am. Nucl. Soc., 30, 336 (1978).
5. R. L. CROWTHER, W. P. PETRICK, and A. WEITZBERG, "Three Dimensional BWR Simulation," Proc. Topl. Mtg. Effective Use of Computers in the Nuclear Industry, Knoxville, Tennessee, April 21-23, 1969, p. 344 (1969).
6. "Two Dimensional Lattice Cell Method," Licensing Topical Report HLR-005, Hitachi Ltd. (1977) (in Japanese).
7. J. T. A. ROBERTS, E. SMITH, N. FUHRMAN, and D. CUBICCIOTTI, "On the Pellet-Cladding Interaction Phenomenon," Nucl. Technol., 35, 131 (1977).
8. F. GELHAUS, J. W. HALLAM, and T. O. SAUAR, "Reactor Fuel Reliability Constraints on Power Shape Control," Nucl. Sci. Eng., 64, 684 (1977).
9. J. P. THOMPSON et al., "Conditioning of Nuclear Reactor Fuel," U.S. Patent 4057466 (1977).
10. J. KOYAMA and M. AOYAMA, "Nodal Expansion Method for Solution of Diffusion Equation in Hexagonal Geometry," J. Nucl. Sci. Technol., 26, 6, 636 (1989).
11. R. D. LAWRENCE, "Progress in Nodal Methods for the Solution of the Neutron Diffusion and Transport Equations," Prog. Nucl. Energy, 17, 271 (1989).