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NRC proposed rule for licensing reactors authorized by DOE, DOD
Nuclear reactor designs approved by the Department of Energy or Department of Defense could get streamlined pathways through the Nuclear Regulatory Commission’s commercial licensing process should applicants wish to push the technology into the civilian sector.
A proposed rule introduced April 2 by the NRC would “improve NRC licensing review efficiency, where applicable, by explicitly establishing by regulation an additional means for reactor applicants to demonstrate the safety functions of their reactor designs, and thus, would contribute to the safe and secure use and deployment of civilian nuclear energy technologies.”
Renato Yoichi Ribeiro Kuramoto, Adimir dos Santos, Rogario Jerez, Ricardo Diniz
Nuclear Science and Engineering | Volume 158 | Number 3 | March 2008 | Pages 272-283
Technical Paper | doi.org/10.13182/NSE06-120
Articles are hosted by Taylor and Francis Online.
A new method for absolute measurement of the effective delayed neutron fraction eff based on Rossi- experiments and the two-region model was developed at the IPEN/MB-01 Research Reactor facility. In contrast with other techniques such as the slope method, the Nelson-number method, and the 252Cf-source method, the main advantage of this new methodology is to obtain the effective delayed neutron parameters in a purely experimental way, eliminating all parameters that are difficult to measure or calculate. In this way, Rossi- experiments for validation of this method were performed at the IPEN/MB-01 facility, and with the use of the present approach, eff was measured with a 1.46% uncertainty. In addition, the prompt neutron generation time and other parameters were also obtained in an absolute experimental way. In general, the final results agree well with values from frequency analysis experiments. Comparison of theory and experiment reveals that JENDL-3.3 shows deviation for eff lower than 1%, which meets the desired accuracy for the theoretical determination of this parameter. This work supports the reduction of the 235U thermal yield, as proposed by Okajima and Sakurai.