Verification of the tables for control rods calibration at NSRR

Motome, Yuiko; Agake, Toshiki; Yanagisawa, Hiroshi

JAEA-Technology 2024-015, 30 Pages, 2025/01

JAEA-Technology-2024-015.pdf:1.36MB

The tables for calibration of control rods were verified, which is used positive period method and improved rod drop method of periodic inspection at Nuclear Safety Research Reactor (NSRR). Those tables are "DOUBLING TIME-REACTIVITY" and "DECAY OF NEUTRON FLUX AFTER INSTANTANEOUS REDUCTION OF REACTIVITY". They are prepared around 1975. Since those tables do not clearly express source of values and records of data used in calculations, the authors verified those tables again. For the verification, the tables were reproduced as follows. For the positive period method, the relationship between the period and reactivity was analytically evaluated by using the inhour equation with NSRR's parameters. For the improved rod drop method, the ratios of neutron flux after the rod drop with parameters of negative reactivities was calculated using the EUREKA- 2 code. As a result, the values described in the tables well agree with those by the present evaluation because it is confirmed that standard deviations of the differences in the value by between the present evaluation and the tables are less than 0.035%. For this reason, it is verified that these tables are valid in the practical use for NSRR operations.

Transient behavior of low enriched uranium silicide miniplate fuel under a triplet configuration

Yanagisawa, Kazuaki;

Journal of Nuclear Science and Technology, 32(10), p.981 - 988, 1995/10

https://doi.org/10.3327/jnst.32.981

no abstracts in English

Analysis of the SPERT III E-core Experiment Using the EUREKA-2 code

; ;

JAERI-M 86-136, 84 Pages, 1986/09

JAERI-M-86-136.pdf:1.65MB

no abstracts in English

A Computer Code for the Reaetiving Accident Analysis in a Water Cooled Reactor

; ; ;

JAERI-M 84-074, 62 Pages, 1984/05

JAERI-M-84-074.pdf:1.57MB

no abstracts in English