Boiling Water Reactors

312 books

Evaluation of risk associated with intergranular stress corrosion cracking in boiling water reactor internalsUnknown Author

Evaluation of risk associated with intergranular stress corrosion cracking in boiling water reactor internals

Unknown Author

2000No page data

Investigation and evaluation of stress-corrosion cracking in piping of light water reactor plantsU.S. Nuclear Regulatory Commission. Pipe Crack Study Group

⏱ 1h 40m

Investigation and evaluation of stress-corrosion cracking in piping of light water reactor plants

U.S. Nuclear Regulatory Commission. Pipe Crack Study Group

1979100 pp.

Criteria for safety-related nuclear power plant operator actionsUnknown Author

⏱ 1h 42m

Criteria for safety-related nuclear power plant operator actions

Unknown Author

1982102 pp.

Investigation of the effectiveness of innovative passive safety systems for boiling water reactorsUnknown Author

⏱ 4h 47m

Investigation of the effectiveness of innovative passive safety systems for boiling water reactors

Unknown Author

2000287 pp.

Evaluation of risk associated with intergranular stress corrosion cracking in boiling water reactor internalsUnknown Author

⏱ 3h 20m

Evaluation of risk associated with intergranular stress corrosion cracking in boiling water reactor internals

Unknown Author

2000200 pp.

Integrated plant safety assessment, systematic evaluation program, La Crosse Boiling Water Reactor, Dairyland Power Cooperative, docket no. 50-409U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.

Integrated plant safety assessment, systematic evaluation program, La Crosse Boiling Water Reactor, Dairyland Power Cooperative, docket no. 50-409

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.

1986No page data

Papers presented at the technical briefing session on the boiling water reactor program and the fast reactor program held at Idaho Falls, Idaho, November 1-2, 1955Argonne National Laboratory.

Papers presented at the technical briefing session on the boiling water reactor program and the fast reactor program held at Idaho Falls, Idaho, November 1-2, 1955

Argonne National Laboratory.

1956No page data

Final safety evaluation report related to the certification of the advanced boiling water reactor designUnknown Author

Final safety evaluation report related to the certification of the advanced boiling water reactor design

Unknown Author

1997No page data

Final safety evaluation report related to the certification of the advanced boiling water reactor designUnknown Author

Final safety evaluation report related to the certification of the advanced boiling water reactor design

Unknown Author

1994No page data

Final safety evaluation report related to the certification of the advanced boiling water reactor designUnknown Author

Final safety evaluation report related to the certification of the advanced boiling water reactor design

Unknown Author

1994No page data

Final safety evaluation report related to the certification of the advanced boiling water reactor designUnknown Author

Final safety evaluation report related to the certification of the advanced boiling water reactor design

Unknown Author

1994No page data

Instrumentation availability during severe accidents for a boiling water reactor with a Mark I containmentW. C. Arcieri

⏱ 1h 5m

Instrumentation availability during severe accidents for a boiling water reactor with a Mark I containment

W. C. Arcieri

199265 pp.

Risk comparisons of scheduling preventive maintenance for boiling water reactors during shutdown and power operationsUnknown Author

Risk comparisons of scheduling preventive maintenance for boiling water reactors during shutdown and power operations

Unknown Author

1999No page data

PSEPLOT, a controller for plotting data from the Mark I boiling water reactor pressure suppression experimentGarry S Holman

⏱ 39m

PSEPLOT, a controller for plotting data from the Mark I boiling water reactor pressure suppression experiment

Garry S Holman

197839 pp.

Leak-before-break in water reactor piping and vesselsC. E. Coleman

⏱ 7h 22m

Leak-before-break in water reactor piping and vessels

C. E. Coleman

1990442 pp.

Phenomenon identification and ranking tables (PIRTs) for loss-of-coolant accidents in pressurized and boiling water reactors containing high burnup fuelB. E. Boyack

Phenomenon identification and ranking tables (PIRTs) for loss-of-coolant accidents in pressurized and boiling water reactors containing high burnup fuel

B. E. Boyack

2001No page data

Phenomenon identification and ranking tables (PIRTs) for rod ejection accidents in pressurized water reactors containing high burnup fuelUnknown Author

Phenomenon identification and ranking tables (PIRTs) for rod ejection accidents in pressurized water reactors containing high burnup fuel

Unknown Author

2001No page data

Phenomenon identification and ranking tables (PIRTs) for power oscillations without scram in boiling water reactors containing high burnup fuelUnknown Author

Phenomenon identification and ranking tables (PIRTs) for power oscillations without scram in boiling water reactors containing high burnup fuel

Unknown Author

2001No page data

Determination of the neutron and gamma flux distribution in the pressure vessel and cavity of a boiling water reactorM. Asgari

⏱ 1h 41m

Determination of the neutron and gamma flux distribution in the pressure vessel and cavity of a boiling water reactor

M. Asgari

1990101 pp.

Nuclear power plant control room task analysisUnknown Author

⏱ 1h 58m

Nuclear power plant control room task analysis

Unknown Author

1983118 pp.

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