The calculation of pressure drop and flow distribution within a reactor vessel in a pressurized water nuclear reactor system /

Critical flow velocities for collapse of reactor parallel-plate fuel assemblies /

Miller, D. R.
U.S. Atomic Energy Commission.
General Electric Company.
Knolls Atomic Power Laboratory.

January 1958

"Knolls Atomic Power Laboratory operated for the United States Atomic Energy Commission by General E...

Reactor process flow technical data

Jones, S.S.
Morrissey, J.E.
Manuel, J.L.

February 1962

A computer program is being developed for the solution of general system flow problems. As a complem...

Some methods of calculation of the parameters in the reactor kinetics equations /

Putnam, G. E.
Phillips Petroleum Company. Atomic Energy Division.
National Reactor Testing Station, Idaho (U.S.)

January 1965

"National Reactor Testing Station"--Cover."Mathematics and Computers ; TID-4500, (37th Ed.).""Issued...

Computation of parameters appearing in the reactor kinetics equations /

Henry, A. F.
U.S. Atomic Energy Commission.
Bettis Atomic Power Laboratory.

"Bettis Plant, Pittsburgh, Pa., operated for the U.S. Atomic Energy Commission by Westinghouse Elect...

A mathematical description of activity build-up in the primary coolant system of a pressurized water reactor resulting from the escape of core-contained fission products /

O'Reilly, B. D.
U.S. Atomic Energy Commission.
Bettis Atomic Power Laboratory.

"Bettis Plant, Pittsburgh, Pa., operated for the U.S. Atomic Energy Commission by Bettis Atomic Powe...

Pressure vessel and piping codes applicable to the PWR reactor plant /

Dobinsky, J. F.
Moffette, T. R.
Andrew, M. B.
Westinghouse Electric Corporation.
U.S. Atomic Energy Commission.
Bettis Atomic Power Laboratory.

"Bettis Plant, Pittsburgh, Pa., operated for the U.S. Atomic Energy Commission by Westinghouse Elect...

Radiation damage exposure and embrittlement of reactor pressure vessels /

Shure, K.
Westinghouse Electric Corporation.
U.S. Atomic Energy Commission.
Bettis Atomic Power Laboratory.

"Bettis Atomic Power Laboratory, Pittsburgh, Pa., operated for the U.S. Atomic Energy Commission by ...

The Shippingport Pressurized Water Reactor Project catalog of document abstracts.

Westinghouse Electric Corporation.
U.S. Atomic Energy Commission.
Bettis Atomic Power Laboratory.

"Contract AT-11-1-GEN-14.""Bettis Atomic Power Laboratory, Pittsburgh, PA.; operated for the U.S. At...

Studies of flow distribution in the core of a quarter-scale flow model of the PWR reactor /

Hazard, Herbert R.
Allen, John M. (John Malone), 1921-
U.S. Atomic Energy Commission.
Battelle Memorial Institute.

"Engineering (TID-4500, 12th Ed.).""October 19, 1956.""Report No. BMI-1141."Work performed by the Ba...

A simple method for calculating the maximum size of ductile rupture in pressurized systems /

Ketchum, H. B.
U.S. Atomic Energy Commission.
Westinghouse Electric Corporation.
Bettis Atomic Power Laboratory.

"Bettis Plant, Pittsburgh, Pa., operated for the U.S. Atomic Energy Commission by Westinghouse Elect...

Supplementary model studies of flow distribution in the core of the PWR reactor /

Flanigan, Lawrence J.
Hazard, Herbert R.
U.S. Atomic Energy Commission.
Battelle Memorial Institute.

"Contract No. W-7405-eng-92.""UC-81 Reactors - Power (TID-4500, 13th Ed., Suppl.).""October 7, 1957....

Pressure calculation for two-dimensional flow inside hydraulic structures /

Bernard, Robert S.
United States. Army. Corps of Engineers.
U.S. Army Engineer Waterways Experiment Station.

Sponsored by Defense Nuclear Agency, conducted by U.S. Army of Engineer Waterways Experiment Station...

A simple method for calculating the maximum size of ductile rupture in pressurized systems /

Ketchum, H. B.
U.S. Atomic Energy Commission.
Westinghouse Electric Corporation.
Bettis Atomic Power Laboratory.

"Bettis Plant, Pittsburgh, Pa., operated for the U.S. Atomic Energy Commission by Westinghouse Elect...

STDY-3 : a program for the thermal analysis of a pressurized water nuclear reactor during steady-state operation /

Pyle, R.S.
Westinghouse Electric Corporation.
U.S. Atomic Energy Commission.
Bettis Atomic Power Laboratory.

"Bettis Atomic Power Laboratory, Pittsburgh, Pennsylvania, operated for the U.S. Atomic Energy Commi...

A numerical solution for plane elasticity problems /

Griffin, D. S.
Varga, Richard S.
Westinghouse Electric Corporation.
U.S. Atomic Energy Commission.
Bettis Atomic Power Laboratory.

"Bettis Atomic Power Laboratory, Pittsburgh, Pa., operated for the U.S. Atomic Energy Commission by ...

Critical flow velocities for collapse of reactor parallel-plate fuel assemblies /

Miller, D. R.
U.S. Atomic Energy Commission.
General Electric Company.
Knolls Atomic Power Laboratory.

January 1958

"Knolls Atomic Power Laboratory operated for the United States Atomic Energy Commission by General E...

Reactor process flow technical data

Jones, S.S.
Morrissey, J.E.
Manuel, J.L.

February 1962

A computer program is being developed for the solution of general system flow problems. As a complem...

Some methods of calculation of the parameters in the reactor kinetics equations /

Putnam, G. E.
Phillips Petroleum Company. Atomic Energy Division.
National Reactor Testing Station, Idaho (U.S.)

January 1965

"National Reactor Testing Station"--Cover."Mathematics and Computers ; TID-4500, (37th Ed.).""Issued...

Computation of parameters appearing in the reactor kinetics equations /

Henry, A. F.
U.S. Atomic Energy Commission.
Bettis Atomic Power Laboratory.

"Bettis Plant, Pittsburgh, Pa., operated for the U.S. Atomic Energy Commission by Westinghouse Elect...

A mathematical description of activity build-up in the primary coolant system of a pressurized water reactor resulting from the escape of core-contained fission products /

O'Reilly, B. D.
U.S. Atomic Energy Commission.
Bettis Atomic Power Laboratory.

"Bettis Plant, Pittsburgh, Pa., operated for the U.S. Atomic Energy Commission by Bettis Atomic Powe...

Pressure vessel and piping codes applicable to the PWR reactor plant /

Dobinsky, J. F.
Moffette, T. R.
Andrew, M. B.
Westinghouse Electric Corporation.
U.S. Atomic Energy Commission.
Bettis Atomic Power Laboratory.

"Bettis Plant, Pittsburgh, Pa., operated for the U.S. Atomic Energy Commission by Westinghouse Elect...

Radiation damage exposure and embrittlement of reactor pressure vessels /

Shure, K.
Westinghouse Electric Corporation.
U.S. Atomic Energy Commission.
Bettis Atomic Power Laboratory.

"Bettis Atomic Power Laboratory, Pittsburgh, Pa., operated for the U.S. Atomic Energy Commission by ...

The Shippingport Pressurized Water Reactor Project catalog of document abstracts.

Westinghouse Electric Corporation.
U.S. Atomic Energy Commission.
Bettis Atomic Power Laboratory.

"Contract AT-11-1-GEN-14.""Bettis Atomic Power Laboratory, Pittsburgh, PA.; operated for the U.S. At...

Studies of flow distribution in the core of a quarter-scale flow model of the PWR reactor /

Hazard, Herbert R.
Allen, John M. (John Malone), 1921-
U.S. Atomic Energy Commission.
Battelle Memorial Institute.

"Engineering (TID-4500, 12th Ed.).""October 19, 1956.""Report No. BMI-1141."Work performed by the Ba...

A simple method for calculating the maximum size of ductile rupture in pressurized systems /

Ketchum, H. B.
U.S. Atomic Energy Commission.
Westinghouse Electric Corporation.
Bettis Atomic Power Laboratory.

"Bettis Plant, Pittsburgh, Pa., operated for the U.S. Atomic Energy Commission by Westinghouse Elect...

Supplementary model studies of flow distribution in the core of the PWR reactor /

Flanigan, Lawrence J.
Hazard, Herbert R.
U.S. Atomic Energy Commission.
Battelle Memorial Institute.

"Contract No. W-7405-eng-92.""UC-81 Reactors - Power (TID-4500, 13th Ed., Suppl.).""October 7, 1957....

Pressure calculation for two-dimensional flow inside hydraulic structures /

Bernard, Robert S.
United States. Army. Corps of Engineers.
U.S. Army Engineer Waterways Experiment Station.

Sponsored by Defense Nuclear Agency, conducted by U.S. Army of Engineer Waterways Experiment Station...

A simple method for calculating the maximum size of ductile rupture in pressurized systems /

Ketchum, H. B.
U.S. Atomic Energy Commission.
Westinghouse Electric Corporation.
Bettis Atomic Power Laboratory.

"Bettis Plant, Pittsburgh, Pa., operated for the U.S. Atomic Energy Commission by Westinghouse Elect...

STDY-3 : a program for the thermal analysis of a pressurized water nuclear reactor during steady-state operation /

Pyle, R.S.
Westinghouse Electric Corporation.
U.S. Atomic Energy Commission.
Bettis Atomic Power Laboratory.

"Bettis Atomic Power Laboratory, Pittsburgh, Pennsylvania, operated for the U.S. Atomic Energy Commi...

A numerical solution for plane elasticity problems /

Griffin, D. S.
Varga, Richard S.
Westinghouse Electric Corporation.
U.S. Atomic Energy Commission.
Bettis Atomic Power Laboratory.

"Bettis Atomic Power Laboratory, Pittsburgh, Pa., operated for the U.S. Atomic Energy Commission by ...

Critical flow velocities for collapse of reactor parallel-plate fuel assemblies /

Miller, D. R.
U.S. Atomic Energy Commission.
General Electric Company.
Knolls Atomic Power Laboratory.

January 1958

"Knolls Atomic Power Laboratory operated for the United States Atomic Energy Commission by General E...

Reactor process flow technical data

Jones, S.S.
Morrissey, J.E.
Manuel, J.L.

February 1962

A computer program is being developed for the solution of general system flow problems. As a complem...

Some methods of calculation of the parameters in the reactor kinetics equations /

Putnam, G. E.
Phillips Petroleum Company. Atomic Energy Division.
National Reactor Testing Station, Idaho (U.S.)

January 1965

"National Reactor Testing Station"--Cover."Mathematics and Computers ; TID-4500, (37th Ed.).""Issued...

The calculation of pressure drop and flow distribution within a reactor vessel in a pressurized water nuclear reactor system /

Abstract

Extracted data

The calculation of pressure drop and flow distribution within a reactor vessel in a pressurized water nuclear reactor system /

Abstract

Extracted data

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