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JAEA Reports

A Development of simulation and analytical program for through-diffusion experiments for a single layer of diffusion media

Sato, Haruo

JNC TN8410 2001-003, 40 Pages, 2001/01

JNC-TN8410-2001-003.pdf:1.13MB

A program (TDROCK1.FOR) for simulation and analysis of through-diffusion experiments for a single layer of diffusion media was developed. This program was made by Pro-Fortran language, which was suitable for scientific and technical calculations, and relatively easy explicit difference method was adopted for an analysis. In the analysis, solute concentration in the tracer cell as a function of time that we could not treat to date can be input and the decrease in the solute concentration as a function of time by diffusion from the tracer cell to the measurement cell, the solute concentration distribution in the porewater of diffusion media and the solute concentration in the measurement cell as a function of time can be calculated. In addition, solution volume in both cells and diameter and thickness of the diffusion media are also variable as an input condition. This simulation program could well explain measured result by simulating solute concentration in the measurement cell as a function of time for case which apparent and effective diffusion coefficients were already known. Based on this, the availability and applicability of this program to actual analysis and simulation were confirmed. This report describes the theoretical treatment for the through-diffusion experiments for a single layer of diffusion media, analytical model, an example of source program and the manual.

JAEA Reports

Analysis of the Rossendorf SEG experiments using the JNC route for reactor calculation

Dietze, K.

JNC TN9400 99-089, 20 Pages, 1999/11

JNC-TN9400-99-089.pdf:0.66MB

The integral experiments performed at the Rossendorf fast-thermal coupled reactor RRR/SEG have been reanalyzed using the JNC route for reactor calculation JENDL3.2/SLAROM / CITATION / JOINT / PERKY. The Rossendorf experiments comprise sample reactivity measurements with pure fission products and structural material in five configurations with different neutron and adjoint spectra. The shapes of the adjoint spectra have been designed to get high sensitivities to neutron capture or the scattering effect. The calculated neutron and adjoint spectra are in good agreement with former results obtained with the European route JEF2.2/ECCO/ERANOS. The C/E-values of the central reactivity worths of samples under investigation are given. Deviations in the results of both routes are due to the different libraries, codes, and self-shielding treatments used in the calculations. Results outside of the error are discussed.

JAEA Reports

None

Iida, Takao*

JNC TJ6400 2000-008, 58 Pages, 1999/03

JNC-TJ6400-2000-008.pdf:1.9MB

None

JAEA Reports

Surveys of System Safety Assessment Methods

Sayama, Hayatoshi*; Suzuki, Kazuhiko*; Shimada, Yukiyasu*

PNC TJ1612 95-001, 39 Pages, 1995/03

PNC-TJ1612-95-001.pdf:1.44MB

no abstracts in English

JAEA Reports

None

Tanaka, Hiroshi*

PNC TJ1211 93-007, 64 Pages, 1993/02

PNC-TJ1211-93-007.pdf:1.0MB

None

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