Theoretical calculation of on-site individual dose for Xi'an pulsed reactor nuclear accident emergency
Creators
- 1. Northwest Institute of Nuclear Technology, Xi'an (China)
Description
In order to rapidly assess individual dose of on-site nuclear accident emergency, a theoretical calculation method for Xi'an pulsed reactor nuclear accident emergency was established. Individual dose of response staff was calculated based on the characteristic parameter of XAPR and source items as input data. The results demonstrated that in case of design basis accident individual dose that operation and response staff received in reactor building is very limited, just about 1.78 mSv. In case of extreme hypothesis accident it was above 100 mSv considering 8 hours' working, and dose that emergency environmental monitoring staff received was lower compared to dose inside building, it was 7.97 × 10-6 and 9.95 × 10-2 mSv at 35 m and 100 m boundary from the reactor site respectively. The results could be used as technological data of nuclear accident emergency, and the method could be applied in individual dose assessment of nuclear emergency in practice. (authors)
Additional details
Publishing Information
- Journal Title
- Radiation Protection (Taiyuan)
- Journal Volume
- 34
- Journal Issue
- 2
- Journal Page Range
- p. 91-96, 101
- ISSN
- 1000-8187
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 49042724
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CALCULATION METHODS; CHINA; COMPARATIVE EVALUATIONS; DESIGN-BASIS ACCIDENTS; MONITORING; OPERATION; PULSED REACTORS; PULSES; RADIATION ACCIDENTS; RADIATION DOSES; RADIATION PROTECTION; REACTOR ACCIDENTS; REACTOR SITES
- Descriptors DEC
- ACCIDENTS; ASIA; DOSES; EVALUATION; REACTORS
Optional Information
- Notes
- 1 fig., 4 tabs., 10 refs.