Gamma dose rate estimation and operation management suggestions for decommissioning the reactor pressure vessel of HTR-PM
- Institute of Nuclear and New Energy Technology, Tsinghua, University, Beijing (China)
China is now designing and constructing a high temperature gas cooled reactor-pebble bed module (HTR-PM). In order to investigate the future decommissioning approach and evaluate possible radiation dose, gamma dose rate near the reactor pressure vessel was calculated for different cooling durations using QAD-CGA program. The source term of this calculation was provided by KORIGEN program. Based on the calculated results, the spatial distribution and temporal changes of gamma dose rate near reactor pressure vessel was systematically analyzed. A suggestion on planning decommissioning operation of reactor pressure vessel of HTRPM was given based on calculated dose rate and the Chinese Standard GB18871-2002. (authors)
- Research Organization:
- American Society of Mechanical Engineers - ASME, Nuclear Engineering Division, Environmental Engineering Division, Two Park Avenue, New York, NY 10016-5990 (United States)
- OSTI ID:
- 22535231
- Resource Relation:
- Conference: ICEM2013 - ASME 2013: 15. International Conference on Environmental Remediation and Radioactive Waste Management, Brussels (Belgium), 8-12 Sep 2013; Other Information: Country of input: France; 8 refs
- Country of Publication:
- United States
- Language:
- English
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