Author:
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 138
Book Description
Radionuclide Release Under Specific LWR Accident Conditions: PWR-large, dry containment desing (Zion Plant)
Author:
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 138
Book Description
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 138
Book Description
Radionuclide release under specific LWR accident conditions. volume vi - pwr-large, dry containment design (zion plant).
Author: J. A. Gieseke
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
This is volume 6, dealing with the zion 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 6 of this report deals with the zion power station, a westinghouse pwr housed in a large, dry, high-pressure containment building. the two accident sequences analyzed for the zion plant were selected for comparative purposes rather than as being representative of a wide range of possible physical conditions. the computer codes used in the analyses are those used throughout all volumes of this report and are representative of the state of the art available in 1983. 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 sequoyah pwr (volume 4). the seventh volume will address technical questions raised during peer review meetings sponsored by the nuclear regulatory commission.
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
This is volume 6, dealing with the zion 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 6 of this report deals with the zion power station, a westinghouse pwr housed in a large, dry, high-pressure containment building. the two accident sequences analyzed for the zion plant were selected for comparative purposes rather than as being representative of a wide range of possible physical conditions. the computer codes used in the analyses are those used throughout all volumes of this report and are representative of the state of the art available in 1983. 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 sequoyah pwr (volume 4). the seventh volume will address technical questions raised during peer review meetings sponsored by the nuclear regulatory commission.
Radionuclide release under specific LWR accident conditions. volume v - pwr-large, dry containment design (surry plant recalculations).
Author: J. A. Gieseke
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
This is volume 5, dealing with the surry 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 and physical processes occuring inside reactor systems, including the containment and other buildings. 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. this volume reports the results of the analysis of the surry power station, a westinghouse pwr housed in a large, dry, high-pressure containment building. the specific accident sequences investigated for the surry 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 include the new code march 2. the surry plant was previously examined in this study using an earlier version of the code, march 1.1; those results were reported in volume 1 of this series. other power plants included in the study are peach bottom bwr (volume 2); grand gulf bwr (volume 3); sequoyah pwr (volume 4); and zion pwr (volume 6). the seventh volume will address technical questions raised during peer review meetings sponsored by the nuclear regulatory commission.
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
This is volume 5, dealing with the surry 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 and physical processes occuring inside reactor systems, including the containment and other buildings. 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. this volume reports the results of the analysis of the surry power station, a westinghouse pwr housed in a large, dry, high-pressure containment building. the specific accident sequences investigated for the surry 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 include the new code march 2. the surry plant was previously examined in this study using an earlier version of the code, march 1.1; those results were reported in volume 1 of this series. other power plants included in the study are peach bottom bwr (volume 2); grand gulf bwr (volume 3); sequoyah pwr (volume 4); and zion pwr (volume 6). the seventh volume will address technical questions raised during peer review meetings sponsored by the nuclear regulatory commission.
Radionuclide Release Under Specific LWR Accident Conditions: PWR-large, dry containment design (Surry Plan recalculations)
Author:
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 272
Book Description
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 272
Book Description
Radionuclide Release Under Specific LWR Accident Conditions: PWR-ice condenser containment design
Author:
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 182
Book Description
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 182
Book Description
Radionuclide Release Under Specific LWR Accident Conditions: BWR-MARK I design
Author:
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 234
Book Description
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 234
Book Description
Radionuclide Release Under Specific LWR Accident Conditions: BWR-MARK III design
Author:
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 222
Book Description
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 222
Book Description
Nuclear Safety
Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 618
Book Description
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 618
Book Description
Analysis of Station Blackout Accidents for the Bellefonte Pressurized Water Reactor
Author: R. D. Gasser
Publisher:
ISBN:
Category : Fission products
Languages : en
Pages : 142
Book Description
Publisher:
ISBN:
Category : Fission products
Languages : en
Pages : 142
Book Description
Proceedings of the ... Workshop on Containment Integrity
Author:
Publisher:
ISBN:
Category : Containerization
Languages : en
Pages : 608
Book Description
Publisher:
ISBN:
Category : Containerization
Languages : en
Pages : 608
Book Description