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Result

LOCAS - Loss-of-coolant-accident stresses

This program can be used for the calculation total stresses in prestressed concrete cylindrical walls of nuclear contaiment structures subjected to increased temperature and internal pressure during loss-of-coolant accidents....

Civil engineering

  • 2023
  • R
  • Link
Result

Realistic model of confienment LEAKBOX 2004

parameters during loss of primary or secondary coolant into that space.) properties in nuclear power plant WWER during loos of primary or secondary coolant abnormal conditions. The problem of best estimate evaluation of fa...

JF - Jaderná energetika

  • 2004
  • X
Result

Validation of Advanced Computer Codes for VVER Technology: LB-LOCA Transient in PSB-VVER Facility

. Five experiments were executed, dealing with loss of coolant scenarios (small, intermediate, and large break loss of coolant accidents), a primary-to-secondary leak, regards the large break loss of c...

JF - Jaderná energetika

  • 2012
  • Jx
  • Link
Result

Analysis of scenario 3A.2.2.6: the loss of coolant in the Primary circuit leading to the spillage of the XL / E-1 tube with following transition to scenario 3B.5.2.2: the flooding of hermetic zone

This research report concerns the analysis of one scenario on the full-scaled simulator of the control room in nuclear power plant Dukovany. This scenario is called the loss of coolant in the Primary circuit leading to spillage of t...

Nuclear related engineering; (nuclear physics to be 1.3);

  • 2018
  • O
  • Link
Result

Study of Radiation and LOCA Impact on Concrete Properties

under loss of coolant accident (LOCA). Comparison of radiation damaged and reference...

Nuclear related engineering; (nuclear physics to be 1.3);

  • 2017
  • D
  • Link
Result

Special coolant displacer for displacing and retention of coolant in nuclear fuel

of severe accidents with loss of reactor coolant. In addition to the thermohydraulicCoolant displacement devices are now widely used in many types of nuclear fuels of these devices is only to prevent coolant overf...

Nuclear related engineering; (nuclear physics to be 1.3);

  • 2021
  • P
  • Link
Result

Analysis of a large break loss of coolant accidentat a pressurized water reactor

The paper presents results of a demo analysis of a large-break loss-of-coolant accident (LB LOCA) at a PWR of the Zion NPP. The event, double ended cold leg break, is analyzed using the best estimate method, which has been verified ...

JF - Jaderná energetika

  • 2009
  • Jx
Result

Benchmark exercise on SBLOCA experiment of PWR PACTEL facility

for the benchmark was a small break loss of coolant accident experiment which was performed coolant inventories. For the blind calculation task, the detailed facility descriptions, the measured pressure and heat losses...

JF - Jaderná energetika

  • 2013
  • Jx
  • Link
Result

Analysis of the distribution element

An analysis of the distribution element in the hydraulic system was performed. This element is responsible for the even distribution of the coolant. The transfer of coolant through manually made capillaries of very small dimensions ...

Mechanical engineering

  • 2024
  • Vsouhrn
Result

Partial Service Life Assessment of a Reactor Containment

Time dependent reliability is based on the the creep induced loss of prestress and three variants of the random process models of the load. The critical failure mode is inflation in several types of LOCA (loss of coolant ac...

JM - Inženýrské stavitelství

  • 2005
  • Jx
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