REACTIVITY WORTHS OF ANNULAR CONTROL RODS IN A PRESSURE-TUBE-TYPE HEAVY-WATER LATTICE

被引:7
作者
UEDA, M
MATSUMOTO, M
HAGA, T
机构
[1] POWER REACTOR & NUCL FUEL DEV CORP, MINATO KU, TOKYO, JAPAN
[2] HITACHI LTD, ATOM ENERGY RES LAB, KAWASAKI, JAPAN
关键词
NUCLEAR REACTORS; HEAVY WATER - Control Rods;
D O I
10.13182/NSE77-A26992
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The control rod effect has been experimentally studied in the Deuterium Critical Assembly (DCA) by using annular absorbers that simulate control rods of the FUGEN reactor, a prototype heavy-water-moderated, boiling-light-water-cooled, pressure-tube-type reactor. The DCA cores for this experiment are of the 1. 2%-**2**3**5U-enriched UO//2 lattices, and consist of 28-pin fuel clusters arranged in a square array of 22. 5-cm lattice pitch. The experiment has been carried out with various control rod patterns and with varying coolant void fraction. Experimental results were analyzed by the ″absorption area method.″ The calculated reactivity worth agreed with the experiment within plus or minus 10%. The results were also analyzed by the ″logarithmic derivative method.″ This method more poorly predicted the worths, but described better the flux shape around the rods.
引用
收藏
页码:559 / 570
页数:12
相关论文
共 24 条
[12]  
HACHIYA SY, 1973, T AM NUCL SOC, V16, P267
[13]  
HONECK H, 1961, BNL5826
[14]  
HURWITZ H, 1955, J NUCL ENERGY, V2, P85
[15]  
KANEKO Y, 1971, J NUCL SCI TECHNOL-T, V8, P34, DOI 10.3327/jnst.8.34
[16]   DELAYED NEUTRONS FROM FISSIONABLE ISOTOPES OF URANIUM, PLUTONIUM, AND THORIUM [J].
KEEPIN, GR ;
WIMETT, TF ;
ZEIGLER, RK .
PHYSICAL REVIEW, 1957, 107 (04) :1044-1049
[17]  
KEEPIN GR, 1965, PHYSICS NUCLEAR KINE, P73
[18]  
MIYAWAKI Y, 1974, PNCN9417472 INT AT E
[19]   APPLICATION OF THE ABSORPTION AREA METHOD TO 3-GROUP DIFFUSION THEORY PROBLEMS [J].
PEARLSTEIN, S .
NUCLEAR SCIENCE AND ENGINEERING, 1958, 4 (03) :322-331
[20]   DETERMINATION OF NEUTRON MULTIPLICATION FACTORS AS A FUNCTION OF TEMPERATURE WITH HIGH-TEMPERATURE LATTICE TEST REACTOR [J].
RICHEY, CR ;
OAKES, TJ .
NUCLEAR SCIENCE AND ENGINEERING, 1972, 47 (01) :40-&