Analytical evaluation of dose measurement of critical accident at SILENE (Contract research)
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
Institute for Radioprotection and Nuclear Safety (IRSN) and the OECD Nuclear Energy Agency (NEA) jointly organized SILENE Accident Dosimetry Intercomparison Exercise to intercompare the dose measurement systems of participating countries. Each participating country carried out dose measurements in the same irradiation field, and the measurement results were mutually compared. The authors participated in the exercise to measure the doses of gamma rays and neutron from SILENE by using thermoluminescence dosimeters (TLD's) and an alanine dosimeter. In this examination, the authors derived evaluation formulae for obtaining a tissue-absorbed dose from measured value (ambient dose equivalent) of TLD for neutron. We reported the tissue-absorbed dose computed using this evaluation formula to OECD/NEA. TLD's for neutron were irradiated in the TRACY facility to verify the evaluation formulae. The results of TLD's were compared with the calculations of MCNP and measurements with alanine dose meter. We found that the ratio of the dose by the evaluation formula to the measured value by the alanine dosimeter was 0.94 and the formula agreed within 6%. From examination of this TRACY, we can conclude that the value reported to OECD/NEA has equivalent accuracy. (author)
Availability note (English)
Available from INIS in electronic form; Also available from JAEA; URL: http://jolisf.tokai-sc.jaea.go.jp/pdf/tec/JAERI-Tech-2003-031.pdfFiles
37002604.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 46 p.
- Report number
- JAERI-Tech--2003-031
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 37002604
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- ALANINES; CRITICALITY; GAMMA DOSIMETRY; INTERLABORATORY COMPARISONS; MONTE CARLO METHOD; NEA; NEUTRON DOSIMETRY; RADIATION ACCIDENTS; RADIATION DOSES; SILENE REACTOR; THERMOLUMINESCENT DOSEMETERS
- Descriptors DEC
- ACCIDENTS; AMINO ACIDS; CALCULATION METHODS; CARBOXYLIC ACIDS; DOSEMETERS; DOSES; DOSIMETRY; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; INTERNATIONAL ORGANIZATIONS; LUMINESCENT DOSEMETERS; MEASURING INSTRUMENTS; OECD; ORGANIC ACIDS; ORGANIC COMPOUNDS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; ZERO POWER REACTORS
Optional Information
- Notes
- 11 refs., 24 figs., 19 tabs.; This record replaces 34060932