Histrory of benchmark experiment analysis with Monte Carlo mehtod for nuclear data reliability evaluation

Sakurai, Kiyoshi; Ueki, Kotaro*

Nippon Genshiryoku Gakkai-Shi, 43(4), p.351 - 352, 2001/04

no abstracts in English

Study on improvement of reactor physics analysis method for FBRs with various core concept

*; Kitada, Takanori*; Tagawa, Akihiro*; *; Takeda, Toshikazu*

JNC-TJ9400 2000-006, 272 Pages, 2000/02

JNC-TJ9400-2000-006.pdf:9.69MB

Investigation was made on the follwing three themes as a part of the improvement of reactor physics analysis method for FBR with various core concept. Part 1: Investigation of Error Estimation of Neutron Spectra in FBR and Suggestions to Improve the Accuracy. In order to improve the spectrum unfolding method used in fast experimental reactor JOYO, a trial was made to evaluate the error in the estimated neutron spectrum, cause by cause. And the evaluated errors were summed up to obtain the most probable and reasonable error as possible. The summed up error was found relatively small compared to the error caused by the uncertainty of cross section data: most of the error in the spectrum unfolding method can be attributed to the error in cross sections. It was also found that the error due to the fission spectrum causes a considerable error in the high energy neutron spectrum which is over several MeV. Part 2: Study on Reactor Physics Analysis Method for Gas-Cooled FBR. In gas-cooled FBR, the portion of coolant channels in core volume is larger than sodium-cooled FBR. This leads to strong neutron streaming effects. For sodium-cooled FBR, several methods were proposed to evaluate the neutron streaming effect, however, these methods can not be used directly to gas-cooled reactor because the direction dependent diffusion coefficient becomes infinitive along the direction pararel to the coolant chammel. In this study, a new method is proposed to evaluate the neutron streaming effect, based on the method taking the axial buckling into consideration, which method was originally proposed by Khler. Part 3: Study on Reactor Physics Analysis Method for Water-Cooled FBR An investigation was made on low-moderated water-cooled FBR, on the point that the ordinary used analysis method for FBR may give considerable difference in results in such core. In light water reactors, it is well known that the space dependence of self-shielding effect of heavy nuclides are considerably ...

Experiments and analyses on fuel expansion and bowing reactivity worth in mock-up cores of metallic fueled fast reactors at FCA

Oigawa, Hiroyuki; Iijima, Susumu; *

Journal of Nuclear Science and Technology, 36(10), p.902 - 913, 1999/10

https://doi.org/10.3327/jnst.36.902

no abstracts in English

None

PNC-TJ2222 94-001, 264 Pages, 1994/03

PNC-TJ2222-94-001.pdf:9.07MB

None

Certainty in results of structural analysis

Nakajima, Norihiro; Nishida, Akemi; Kawakami, Yoshiaki; Suzuki, Yoshio

no journal, , 

Quality Assurance is an issue for computational science and engineering. It is well discussed in verification and validation for Simulation. In finite element analysis, it is a problem whether the finite element discretization is appropriate or not. Also, algorithmic choice prepared variously by the recent R&D discipline that become the problem which one to take. An experiment was performed for the static analysis and natural frequency analysis to confirm how uncertainty is revealed. As a result, by means to compare accuracy of the calculation precision that utilized a parallel environment, the numerical experiment reconfirmed that the estimate of the calculation solution was possible.