✦ LIBER ✦

Calculation of Deep Burnup of Nuclear Fuel in Lattices with a Regulatable Neutron Spectrum

✍ Scribed by V. I. Savander; M. A. Uvakin

Publisher: Springer US
Year: 2005
Tongue: English
Weight: 151 KB
Volume: 98
Category: Article
ISSN: 1573-8205
DOI: 10.1007/s10512-005-0224-4

No coin nor oath required. For personal study only.

📜 SIMILAR VOLUMES

Burnup of radioactive nuclear fuel waste

Burnup of radioactive nuclear fuel wastes in a fast neutron flux

✍ V. Ya. Kostin; V. Ya. Migalenya; M. G. Shatnev; A. N. L'vov 📂 Article 📅 1981 🏛 Springer US 🌐 English ⚖ 222 KB

Burnup-dependent core neutronics analysi

Burnup-dependent core neutronics analysis and calculation of actinide and fission product inventories in discharged fuel of a material test research reactor

✍ Siraj-ul-Islam Ahmad; Nasir Ahmad 📂 Article 📅 2006 🏛 Elsevier Science 🌐 English ⚖ 650 KB

The System for Analysis of Reactor Core (SARC) has been developed for burnup analysis of nuclear reactors using whole core modeling and simulation by coupling the WIMS-D4S and CITATION. The system has the capability to use 1981, 1986 and other WIMS-D libraries recently released by International Atom

Comparison of the neutron energy spectru

Comparison of the neutron energy spectrum and neutron fluence rate in the LVR-15 research reactor with fuel with different enrichment

✍ M. Vinš; L. Viererbl; Z. Lahodová; M. Marek; A. Voljanskij; V. Klupák; M. Kolesk 📂 Article 📅 2011 🏛 Springer 🌐 English ⚖ 561 KB

PULSAR+: A program for calculating the b

PULSAR+: A program for calculating the behavior of fuel elements in a nuclear fuel assembly in accidents with coolant losses and reactivity spikes

✍ An. A. Tutnov; Al. A. Tutnov; E. E. Alekseev 📂 Article 📅 1997 🏛 Springer US 🌐 English ⚖ 296 KB

Development of the surface pseudosource

Development of the surface pseudosource method for calculating neutron fields in cells with a bundle of fuel-element rods

✍ N. I. Laletin; N. V. Sultanov 📂 Article 📅 1979 🏛 Springer US 🌐 English ⚖ 529 KB

04/01071 Core burnup calculation and acc

04/01071 Core burnup calculation and accidents analyses of a pressurized water reactor partially loaded with rock-like oxide fuel: Akie, H. et al. Journal of Nuclear Materials, 2003, 319, (1), 166–172

📂 Article 📅 2004 🏛 Elsevier Science ⚖ 192 KB

16 Fuel science and technology (fundamental science, analysis, instrumentation) content of higher than 30% and heat losses of more than 15% should be avoided. For the above parameters, the gasification zone should be 33 cm long to achieve an acceptable conversion efficiency. ## 04/01070 Contact an