http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
- 中文 을 입력하시려면 zhongwen을 입력하시고 space를누르시면됩니다.
- 北京 을 입력하시려면 beijing을 입력하시고 space를 누르시면 됩니다.
RISS 인기검색어
- 검색키워드
- 저자 : S. C. van der Marck (검색결과 3 건)
- 무료
- 기관 내 무료
- 유료
-
Exact Nuclear Data Uncertainty Propagation for Fusion Design
D. Rochman,A. J. Koning,S. C. van der Marck 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
Recently, we have presented an exact method (now called ``Total Monte Carlo'') to propagate uncertainties of fundamental nuclear physics experiments, models and parameters to large and complicated nuclear systems. We now show that such exact uncertainty calculations are directly relevant to the optimal and safe design of fusion systems by applying this methodology to a series of fusion shielding benchmarks, namely those connected to the Oktavian, FNS and LLNL experiments. Uncertainties on neutron and gamma leakage fluxes for shielding benchmarks are obtained. Uncertainties for cross sections, angular distributions, single- and double-differential emission spectra, and gamma-ray production cross sections are considered.
-
Nuclear Data Uncertainty Propagation: Total Monte Carlo vs. Covariances
D. Rochman,A. J. Koning,S. C. van der Marck,A. Hogenbirk,D. van Veen 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
Two distinct methods of propagation for basic nuclear data uncertainties to large scale systems will be presented and compared. The "Total Monte Carlo" method is using a statistical ensemble of nuclear data libraries randomly generated by means of a Monte Carlo approach with the TALYS system. These libraries are then directly used in a large number of reactor calculations (for instance with MCNP) after which the exact probability distribution for the reactor parameter is obtained. The second method makes use of available covariance files and can be done in a single reactor calculation (by using the perturbation method). In this exercise, both methods are using consistent sets of data files, which implies that covariance files used in the second method are directly obtained from the randomly generated nuclear data libraries from the first method. This is a unique and straightforward comparison allowing to directly apprehend advantages and drawbacks of each method. Comparisons for different reactions and criticality-safety benchmarks from ^(19)F to actinides will be presented. We can thus conclude whether current methods for using covariance data are good enough or not.
-
Nuclear Data Uncertainty Propagation for a Sodium Fast Reactor
D. Rochman,A. J. Koning,D. F. Dacruz,S. C. van der Marck 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
Nuclear data uncertainties are propagated from basic theory to a full core model of the Kalimer-600 Korean type Sodium Fast Reactor (SFR) using the TALYS nuclear code system, the "Total Monte Carlo" (TMC) approach and perturbation methods developed at NRG. Nuclear data uncertainties from sodium, iron, and some actinides will be presented together with their impact on parameters such as the sodium void coefficient and k<sub>eff</sub>. One of the advantages of the TMC method is that it avoids approximations used in perturbation theories, by applying an exact uncertainty propagation approach. Additionally, full nuclear data uncertainties (cross sections, nu-bar as well as single and double differential data) can be considered.
연관 검색어 추천
이 검색어로 많이 본 자료
활용도 높은 자료
