1. BURNUP CALCULATION FOR A TOKAMAK COMMERCIAL HYBRID REACTOR.

2. The possible benefit of average discharged burnup is calculated as well. The study shows that if the advanced fuel management strategy is employed, a remarkable efficien...

3. For reactors loaded with fuel assemblies of different burnup, the evaluation model can te used to calculate core physical parameters such as core neutron multiplication factor, burnup increment, etc.

4. The relationship between burnup and neutron emission intensity of the irradiated low-enrichment uranium oxide fuel was analyzed and studied.

5. ORIGEN2,[http://] for the multi region burnup calculation of the blanket by using the one group effective cross section provided in the output of MCNP4A.

6. The various methods currently being used in burnup determination of nuclear fuels are studyed and reviewed, The mass spectrometry method of destructive testing is discussed emphatically.

7. The present invention provides a burnup saving type engine oil with superior low vaporability and low temperature viscosity property.

8. To calculate burnup for the cores with fast neutron spectrum, we have written the linking codes to process the input and output of MCNP code and ORIGEN2 code.

9. The code was employed to optimize the cycle length, the peak power factor and the discharge burnup of the first cycle loading for the Daya Bay Nuclear Plant.

10. These methods contribute to understand irradiation behavior of fuel, cladding and structure components and supply proof for increasing burnup.

11. The theoretical models of a program NDHEXB for fast reactor burnup calculations isdescribed.

12. Meanwhile the early and later irradiation experiences of metallic fuels were summarized, including the limits of burnup which had been demonstrated.

13. TPFAP is a transmisssion probabilily fuel assembly code package for burnup calculations on BWR and PWR.

14. This method can achieve objectives of increasing cycle length, increasing average discharge burnup, and decreasing power peak factor.

15. This paper represents the analysis and calculation of thermal group parameters of gadolinium oxide as burnable poison, and characteristics of energy spectrum with change of burnup.

16. This software is used to simulate the ship reactor with hexagonal fuel subassembly after 10,150 and 200 burnup days, considering the hydraulic and thermal feedback.

17. Threeequivalent methods are studied, in which a few imaginary fission products. Inthis method the maximum error of the reactivity effect process is only about 2%in the whole burnup.

18. One of the way to enhance the economic benefit for nuclear power plant is to deepen burnup and extend reload cycle.

19. In this paper, a set of important formulae for burnup determination of fuel element from HFETR are deduced and researched, and main formulae of ASTM E244 are reformed.

20. Since Monte Carlo code cannot be applied to calculate the isotopic composition of burned fuel, a new algorithm combined with the depletion code is proposed to calculate burnup.