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Showing 1 to 7 of 7 for “"emergency core cooling system"”.

  1. Risk-informed design guidance for a Generation-IV gas-cooled fast reactor emergency core cooling system

    … advanced reactor. However, an advanced reactor's core damage frequency dominates all other considerations at the preliminary stage of reactor design. An iterative four-step methodology to guide the MIT gas-cooled fast reactor emergency core cooling system design through PRA insights was utilized …

    mit Repository record for Risk-informed design guidance for a Generation-IV gas-cooled fast reactor emergency core cooling system (opens in a new tab)

  2. Use of fuel cells for improving on-site emergency power availability and reliability ad nuclear power plants

    … heat removal provided, in last resort, by an Emergency Core Cooling System (ECCS). Currently the majority of nuclear power plants in the US utilize diesel generator sets as on-site emergency power generating units. In addition to the loss of off-site power, plants can lose their on-site AC …

    mit Repository record for Use of fuel cells for improving on-site emergency power availability and reliability ad nuclear power plants (opens in a new tab)

  3. Pool boiling heat transfer characteristics of nanofluids

    … main reactor coolant for PWR, coolant for the Emergency Core Cooling System (ECCS) of both PWR and BWR, and coolant for in-vessel retention of the molten core during severe accidents in high-power-density LWR. To implement such applications it is necessary to understand the fundamental boiling …

    mit Repository record for Pool boiling heat transfer characteristics of nanofluids (opens in a new tab)

  4. Simulation and Validation of Two-Component Flow in a Void Recirculation System

    <p>Nuclear power plants rely on the Emergency Core Cooling System (ECCS) to cool down the reactor core in case of an accident. Occasionally, air is entrained into the suction piping of ECCS causing voids that decrease pumping efficiency, and consequently damage the pumps. In an attempt to minimize …

    calpoly Repository record for Simulation and Validation of Two-Component Flow in a Void Recirculation System (opens in a new tab)

  5. The use of reduced-moderation light water reactors for transuranic isotope burning in thorium fuel

    … (LWRs) are the world’s dominant nuclear reactor system. Uranium (U)-fuelled LWRs produce long-lived transuranic (TRU) isotopes. TRUs can be recycled in LWRs or fast reactors. The thermal neutron spectrum in LWRs is less suitable for burning TRUs as this causes a build-up of TRU isotopes with low …

    cambridge Repository record for The use of reduced-moderation light water reactors for transuranic isotope burning in thorium fuel (opens in a new tab)

  6. The Formulation and solution of Time Variant Markov Models for Probabilistic Risk Analysis

    Made available in DSpace on 2017-07-06T18:59:34Z (GMT). No. of bitstreams: 3 Wyss_Gregory_D_MS.pdf: 50131364 bytes, checksum: 183c14c9ccf220e6f4e29914af6413b6 (MD5) Wyss_Gregory_D_MS_ABS.pdf: 556067 bytes, checksum: a8a42ef7e3157e50f7707c600e64cd48 (MD5) license.txt: 4813 bytes, checksum: …

    uiuc Repository record for The Formulation and solution of Time Variant Markov Models for Probabilistic Risk Analysis (opens in a new tab)

  7. Effect of helium injection on diffusion dominated air ingress accidents in pebble bed reactors

    … experiencing a similar accident will have the core entirely filled with helium. Thus, for a vertically oriented double ended guillotine (DEG) large-break loss of coolant accident (LB-LOCA) the subsequent air ingress rate will be dictated by the slow diffusion of air into the reactor cavity, for …

    mit Repository record for Effect of helium injection on diffusion dominated air ingress accidents in pebble bed reactors (opens in a new tab)