Uncertainty Evaluation of Effective Delayed Neutron Fraction β_<eff> of Typical Proto-type Fast Reactor
スポンサーリンク
概要
- 論文の詳細を見る
Uncertainty of effective delayed neutron fraction βeff is evaluated in terms of three quantities; uncertainties of the basic delayed neutron constants, energy dependence of delayed neutron yield νmd in the low energy side below about 50 keV and in the high energy side above about 4 MeV, and the uncertainties of the fission cross sections of fuel elements. The uncertainty of βeff due to the delayed neutron yield is expressed by a linearized formula assuming that the delayed neutron yield does not depend on the incident energy, and the energy dependence is supplemented by using the detailed energy dependence proposed by DAngelo and Filip. The third quantity, uncertainties of fission cross section, is evaluated on the basis of the generalized perturbation theory in relation to reaction rate ratios such as central spectral indexes or average reaction rate ratios. Sensitivity coefficients of the reaction rate ratios to fission cross sections are abtained by generalized perturbation code. Resultant uncertainty of βeff is about 4 to 5%, in which primary factor is the delayed neutron yield, and the secondary one is the fission cross section uncertainty, especially for 238U. The energy dependence of νmd systematically reduces the magnitude of βeff about 1.4 to 1.7%, depending on the model of the energy vs. νmd correlation curve.
- 社団法人 日本原子力学会の論文
- 1999-01-25
著者
-
ZUKERAN Atsushi
Power & Insdustrial System R&D Division, Hitachi, Ltd.
-
Zukeran Atsushi
Power & Industrial System R & D Division Hitachi Ltd.
-
HANAKI Hiroshi
Fast Breeder Engineering Department, Hitachi Works, Hitachi, Ltd.
-
SAWADA Shusaku
Reactor and Systems Engineering Section, Monju Construction Office, Power Reactor and Nuclear Fuel D
-
SUZUKI Takayuki
Reactor and Systems Engineering Section, Monju Construction Office, Power Reactor and Nuclear Fuel D
-
Hanaki Hiroshi
Fast Breeder Engineering Department Hitachi Works Hitachi Ltd.
-
Sawada Shusaku
Reactor And Systems Engineering Section Monju Construction Office Power Reactor And Nuclear Fuel Dev
-
Suzuki T
Reactor And Systems Engineering Section Monju Construction Office Power Reactor And Nuclear Fuel Dev
関連論文
- Simultaneous Evaluation of Fission Cross Sections of Uranium and Platonium Isotopes for JENDL-3.3
- Re-evaluation of Nuclear Data of Fission Product Nuclides for JENDL-3.2
- Uncertainty Evaluation of Effective Delayed Neutron Fraction β_ of Typical Proto-type Fast Reactor