Nuclear criticality benchmark analyses on TRIGA-type reactor systems by using continuous-energy Monte Carlo code MVP with JENDL-5

Yanagisawa, Hiroshi; Umeda, Miki; Motome, Yuiko; Murao, Hiroyuki

JAEA-Technology 2022-030, 80 Pages, 2023/02

JAEA-Technology-2022-030.pdf:2.57MB

Nuclear criticality benchmark analyses were carried out for TRIGA-type reactor systems in which uranium-zirconium hydride fuel rods are loaded by using the continuous-energy Monte Carlo code MVP with the evaluated nuclear data library JENDL-5. The analyses cover two sorts of benchmark data, the IEU-COMP-THERM-003 and IEU-COMP-THERM-013 in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook, and effective neutron multiplication factors, reactivity worths for control rods etc. were calculated by JENDL-5 in comparison with those by the previous version of JENDL. As the results, it was confirmed that the effective neutron multiplication factors obtained by JENDL-5 were 0.4 to 0.6% greater than those by JENDL-4.0, and that there were no significant differences in the calculated reactivity worths by between JENDL-5 and JENDL-4.0. Those results are considered to be helpful for the confirmation of calculation accuracy in the analyses on NSRR control rod worths, which are planned in the future.

Characteristic test of initial HTTR core

Nojiri, Naoki; Shimakawa, Satoshi; Fujimoto, Nozomu; Goto, Minoru

Nuclear Engineering and Design, 233(1-3), p.283 - 290, 2004/10

https://doi.org/10.1016/j.nucengdes.2004.08.015

This paper describes the results of core physics test in start-up and power-up of the HTTR. The tests were conducted in order to ensure performance and safety of the high temperature gas cooled reactor, and was carried out to measure the critical approach, the excess reactivity, the shutdown margin, the control rod worth, the reactivity coefficient, the neutron flux distribution and the power distribution. The expected core performance and the required reactor safety characteristics were verified from the results of measurements and calculations.

The Present active status of domestic critical assemblies and the perspective for their future, 2-4; Very high temperature reactor critical assembly (VHTRC)

Akino, Fujiyoshi; Yamane, Tsuyoshi

Nihon Genshiryoku Gakkai-Shi, 40(4), p.262 - 264, 1998/00

no abstracts in English

Experimental verification and analysis of neutron streaming effect through void holes for control rod insertion in HTTR

Akino, Fujiyoshi; Takeuchi, Motoyoshi; Ono, Toshihiko; Kaneko, Yoshihiko

Journal of Nuclear Science and Technology, 34(2), p.185 - 192, 1997/02

https://doi.org/10.3327/jnst.34.185

no abstracts in English

Neutronics properties of JMTR LEU core

Nagaoka, Yoshiharu; Saito, Minoru;

Transactions of the American Nuclear Society, 66, p.454 - 455, 1992/11

no abstracts in English

Experimental study of power distribution in FCA XV cores with half-inserted BC control rod

Oigawa, Hiroyuki; Osugi, Toshitaka; Ono, Akio; ; *

JAERI-M 91-096, 39 Pages, 1991/06

JAERI-M-91-096.pdf:0.85MB

no abstracts in English

Development and valiation of nuclear design code system for High Temperature Engineering Test Reactor (HTTR)

Yamashita, Kiyonobu; Shindo, Ryuichi; Murata, Isao

The Safety,Status and Future of Non-Commercial Reactors and Irradiation Facilities,Vol. 1, p.350 - 358, 1990/09

no abstracts in English

Nuclear Characteristic Measurement and Calsulation by the SRAC Code System for LEU Fuel Element

; ; ; ;

JAERI-M 85-047, 81 Pages, 1985/04

JAERI-M-85-047.pdf:1.98MB

no abstracts in English

Study of Control Rod Worth Evaluation Model for VHTR Design

*

JAERI-M 9433, 109 Pages, 1981/04

JAERI-M-9433.pdf:3.01MB

no abstracts in English

Reference Core Design of the ExperimentalMulti; Purpose VHTR-Mark-III Core Nuclear Characteristics

; ; *; *; *; *

JAERI-M 8293, 101 Pages, 1979/06

JAERI-M-8293.pdf:3.01MB

no abstracts in English

Estimation of multiple control rod worth with strong interaction effect in large fast reactors

Journal of Nuclear Science and Technology, 13(9), p.517 - 520, 1976/09

https://doi.org/10.3327/jnst.13.517

no abstracts in English