Author:
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 234
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
Radionuclide release under specific LWR accident conditions. volume iii - bwr, mark iii design
Author: J. A. Gieseke
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
This is volume 3, dealing with the grand gulf 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 3 of this report deals with the grand gulf power station, a general electric bwr, mark iii containment design. the specific accident sequences investigated for the grand gulf 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); 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 3, dealing with the grand gulf 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 3 of this report deals with the grand gulf power station, a general electric bwr, mark iii containment design. the specific accident sequences investigated for the grand gulf 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); 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. volume ii - bwr, mark i design
Author: J. A. Gieseke
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
This is volume 2, dealing with the peach bottom 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 2 of this report deals with the peach bottom 2 power station, a general electric bwr, mark i containment design. the specific accident sequences investigated for the peach bottom 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); grand gulf bwr (volume 3); sequoyah pwr (volume 4); and zion pwr (volume 6). the seventh volume will address technical questions raised during the peer review of this effort.
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
This is volume 2, dealing with the peach bottom 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 2 of this report deals with the peach bottom 2 power station, a general electric bwr, mark i containment design. the specific accident sequences investigated for the peach bottom 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); grand gulf bwr (volume 3); sequoyah pwr (volume 4); and zion pwr (volume 6). the seventh volume will address technical questions raised during the peer review of this effort.
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
Author:
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 298
Book Description
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 298
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
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
Title List of Documents Made Publicly Available
Author:
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 1052
Book Description
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 1052
Book Description
Fission Product Processes In Reactor Accidents
Author: J. T. Rogers
Publisher: CRC Press
ISBN: 1000158624
Category : Science
Languages : en
Pages : 742
Book Description
The Three Mile Island and Chernobyl nuclear incidents emphasized the need for the world-wide nuclear community to cooperate further and exchange the results of research in this field in the most open and effective manner. Recognizing the roles of heat and mass transfer in all aspects of fission-product behavior in sever reactor accidents, the Executive Committee of the International Centre for Heat and Mass Transfer organized a Seminar on Fission Product Transport Processes in Reactor Accidents. This book contains the eleven of the lectures and all the papers presented at the seminar along with four invited papers that were not presented and a summary of the closing session.
Publisher: CRC Press
ISBN: 1000158624
Category : Science
Languages : en
Pages : 742
Book Description
The Three Mile Island and Chernobyl nuclear incidents emphasized the need for the world-wide nuclear community to cooperate further and exchange the results of research in this field in the most open and effective manner. Recognizing the roles of heat and mass transfer in all aspects of fission-product behavior in sever reactor accidents, the Executive Committee of the International Centre for Heat and Mass Transfer organized a Seminar on Fission Product Transport Processes in Reactor Accidents. This book contains the eleven of the lectures and all the papers presented at the seminar along with four invited papers that were not presented and a summary of the closing session.