Radionuclide Release Under Specific LWR Accident Conditions: PWR-ice condenser containment design

Radionuclide Release Under Specific LWR Accident Conditions: PWR-ice condenser containment design PDF Author:
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 182

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Radionuclide Release Under Specific LWR Accident Conditions: PWR-ice condenser containment design

Radionuclide Release Under Specific LWR Accident Conditions: PWR-ice condenser containment design PDF Author:
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 182

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Radionuclide release under specific LWR accident conditions. volume iv - pwr, ice condenser containment design

Radionuclide release under specific LWR accident conditions. volume iv - pwr, ice condenser containment design PDF Author: J. A. Gieseke
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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This is volume 4, dealing with the sequoyah nuclear power plant, of a seven-volume report of work done at battelle's columbus laboratories to estimate the amount of radioactive material that could be released from light water reactor (lwr) power plants under specific, hypothetical accident conditions. to make these estimates, five power plants were selected that represent the major categories of lwrs: three pressurized water reactors (pwrs) and two boiling water reactors (bwrs). specifications and data from these plants, along with data from laboratory experiments, were input to computer codes designed to describe various conditions prevailing inside an operating reactor. ultimately, these computer codes provide an estimate of how much radioactive material would be able to escape to the environment if a specific series of events (an "accident sequence") took place. volume 4 of this report deals with the sequoyah power station, a westinghouse pwr with an ice condenser containment. the specific accident sequences investigated for the sequoyah plant were selected to represent cases of high risk, severe consequences, and most importantly,a wide range of physical conditions. the computer codes used to analyze the accident sequences were the best available, including the new march 2 code. other power plants included in the study are surry pwr (volumes 1 and 5); peach bottom bwr (volume 2); grand gulf bwr (volume 3); and zion pwr (volume 6). the seventh volume will address technical questions raised as a results of the peer review of this work during its performance.

Radionuclide Release Under Specific LWR Accident Conditions: PWR-large, dry containment design (Surry Plan recalculations)

Radionuclide Release Under Specific LWR Accident Conditions: PWR-large, dry containment design (Surry Plan recalculations) PDF Author:
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 272

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Radionuclide Release Under Specific LWR Accident Conditions: PWR-large, dry containment desing (Zion Plant)

Radionuclide Release Under Specific LWR Accident Conditions: PWR-large, dry containment desing (Zion Plant) PDF Author:
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 138

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Radionuclide Release Under Specific LWR Accident Conditions

Radionuclide Release Under Specific LWR Accident Conditions PDF Author:
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 298

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Radionuclide Release Under Specific LWR Accident Conditions: BWR-MARK I design

Radionuclide Release Under Specific LWR Accident Conditions: BWR-MARK I design PDF Author:
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 234

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Radionuclide Release Under Specific LWR Accident Conditions: BWR-MARK III design

Radionuclide Release Under Specific LWR Accident Conditions: BWR-MARK III design PDF Author:
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 222

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Nuclear Safety

Nuclear Safety PDF Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 618

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Advances in Heat Transfer

Advances in Heat Transfer PDF Author:
Publisher: Academic Press
ISBN: 0080575838
Category : Technology & Engineering
Languages : en
Pages : 375

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Book Description
Advances in Heat Transfer is designed to fill the information gap between regularly scheduled journals and university level textbooks by providing in-depth review articles over a broader scope than is allowablein either journals or texts. Volume 29 is a special volume devoted to nuclear reactor safety.

Proceedings of the U.S. Nuclear Regulatory Commission ... Water Reactor Safety Research Information Meeting

Proceedings of the U.S. Nuclear Regulatory Commission ... Water Reactor Safety Research Information Meeting PDF Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 464

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