HWZPR is a research reactor with natural uranium fuel, D2O moderator and graphite reflector with maximum power of 100 W. It is a suitable means for theoretical research and heavy water reactor experiments. Neutrons from the core participate in different nuclear reactions by interactions with fuel, moderator, graphite and the concrete around the reactor. The results of these interactions are the production of prompt gammas in the environment. Useful information is gained by the reactor gamma spectrum measurement from point of view of relative quantity and energy distribution of direct and scattered radiations. Reactor gamma ray spectrum has been gathered in different places around the reactor by HPGe detector. In analysis of these spectra, 1H(n,γ)2H, 16O(n,n′γ)16O, 2H(n,γ)3H and 238U(n,γ)239U reactions occurring in reactor moderator and fuel, are important. The measured spectrum has been primarily estimated by the MCNP code. There is agreement between the code and the experiments in some points. The scattered gamma rays from 27Al (n,γ)28Al reaction in the reactor tank, are the most among the gammas scattered in the reactor environment. Also the dose calculations by MCNP code show that 72% of gamma dose belongs to the energy range 3–11 MeV from reactor gamma spectrum and the danger of exposure from the reactor high-energy photons is serious.
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14th International Conference on Nuclear Engineering
July 17–20, 2006
Miami, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4244-4
PROCEEDINGS PAPER
Measurement and Calculation of Gamma Radiation from HWZPR Reactor Available to Purchase
Majid Jalali
Majid Jalali
Atomic Energy Organization of Iran, Esfahan, Iran
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Majid Jalali
Atomic Energy Organization of Iran, Esfahan, Iran
Paper No:
ICONE14-89091, pp. 343-346; 4 pages
Published Online:
September 17, 2008
Citation
Jalali, M. "Measurement and Calculation of Gamma Radiation from HWZPR Reactor." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy. Miami, Florida, USA. July 17–20, 2006. pp. 343-346. ASME. https://doi.org/10.1115/ICONE14-89091
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