Analysis of gamma irradiator dose rate using spent fuel elements with parallel configuration
Creators
- 1. Pusat Teknologi Reaktor dan Keselamatan Nuklir – BATAN, Serpong (Indonesia)
Description
To enhance the utilization of the RSG-GAS reactor spent fuel, the gamma irradiator using spent fuel elements as a gamma source is a suitable choice. This irradiator can be used for food sterilization and preservation. The first step before realization, it is necessary to determine the gamma dose rate theoretically. The assessment was realized for parallel configuration fuel elements with the irradiation space can be placed between fuel element series. This analysis of parallel model was choice to compare with the circle model and as long as possible to get more space for irradiation and to do manipulation of irradiation target. Dose rate calculation were done with MCNP, while the estimation of gamma activities of fuel element was realized by OREGEN code with 1 year of average delay time. The calculation result show that the gamma dose rate of parallel model decreased up to 50% relatively compared with the circle model, but the value still enough for sterilization and preservation. Especially for food preservation, this parallel model give more flexible, while the gamma dose rate can be adjusted to the irradiation needed. The conclusion of this assessment showed that the utilization of reactor spent fuels for gamma irradiator with parallel model give more advantage the circle model. (author)
Additional details
Additional titles
- Original title (Indonesian)
- Analisis laju dosis irradiator gamma menggunakan elemen bakar dengan model konfigurasi sejajar
Publishing Information
- Journal Title
- Jurnal Teknologi Reaktor Nuklir
- Journal Volume
- 8
- Journal Issue
- 3
- Journal Page Range
- p. 148-160
- ISSN
- 1411-240X
INIS
- Country of Publication
- Indonesia
- Country of Input or Organization
- Indonesia
- INIS RN
- 48079880
- Subject category
- S07: ISOTOPES AND RADIATION SOURCES;
- Descriptors DEI
- DOSE RATES; GAMMA RADIATION; MONTE CARLO METHOD; PRESERVATION; PROGRAMMING; RADIATION DOSES; SPENT FUEL ELEMENTS
- Descriptors DEC
- CALCULATION METHODS; DOSES; ELECTROMAGNETIC RADIATION; FUEL ELEMENTS; IONIZING RADIATIONS; RADIATIONS; REACTOR COMPONENTS
Optional Information
- Notes
- 9 refs., 7 tabs., 6 figs.