computer program DYNAPCON for the transient analysis of a prestressed concrete reactor vessel (PCRV) for liquid-metal fast breeder reactor (LMFBR) primary containment is applied to a reference design concept representative of large, pool-type LMFBR reactor plants. Estimates of the energy absorption capability of a PCR V primary containment vessel are provided to assist in the establishment of the engineering feasibility of such a design concept. The reference design analyzed utilizes existing concrete stnlctures already in place for biological shielding and component support. The very large INTROOUCTION Marchertas and Belytschko I have described th
The containment is an ultimate and important barrier to mitigate the consequences after the release ...
Design optimization studies indicate that a significant reduction in the size of the PCRV for a 2240...
The core concrete interaction (CCI) is an important phase of any severe accident where the reactor v...
Reported are preliminary results of a study at the Argonne National laboratory, the objective of whi...
The paper discusses special features of the concept of a dried hot prestressed concrete reactor vess...
An analytical model of a prestressed concrete reactor vessel (pCR V) for LMFBR ilnd the associated f...
A finite element computer code for the transient analysis of prestressed concrete reactor vessels (P...
This lecture reviews new developments in analysis and design of prestressed concrete reactor vessels...
Static overpressurization tests of two scale models of nuclear containment structures - a steel cont...
Two single-cavity prestressed concrete reactor vessel (PCRV) models were fabricated and tested to fa...
In light of the scientific evidence for changes in the climate caused by greenhouse-gas emissions fr...
Thesis. 1975. M.S.--Massachusetts Institute of Technology. Dept. of Civil Engineering.Bibliography: ...
This report explores the requirements for the design and analysis of concrete containment and shows ...
Those areas or cells within LMFBR plants that contain radioactive sodium systems are provided with c...
The general objective of the study is to perform a diversion analysis and an assessment of the avail...
The containment is an ultimate and important barrier to mitigate the consequences after the release ...
Design optimization studies indicate that a significant reduction in the size of the PCRV for a 2240...
The core concrete interaction (CCI) is an important phase of any severe accident where the reactor v...
Reported are preliminary results of a study at the Argonne National laboratory, the objective of whi...
The paper discusses special features of the concept of a dried hot prestressed concrete reactor vess...
An analytical model of a prestressed concrete reactor vessel (pCR V) for LMFBR ilnd the associated f...
A finite element computer code for the transient analysis of prestressed concrete reactor vessels (P...
This lecture reviews new developments in analysis and design of prestressed concrete reactor vessels...
Static overpressurization tests of two scale models of nuclear containment structures - a steel cont...
Two single-cavity prestressed concrete reactor vessel (PCRV) models were fabricated and tested to fa...
In light of the scientific evidence for changes in the climate caused by greenhouse-gas emissions fr...
Thesis. 1975. M.S.--Massachusetts Institute of Technology. Dept. of Civil Engineering.Bibliography: ...
This report explores the requirements for the design and analysis of concrete containment and shows ...
Those areas or cells within LMFBR plants that contain radioactive sodium systems are provided with c...
The general objective of the study is to perform a diversion analysis and an assessment of the avail...
The containment is an ultimate and important barrier to mitigate the consequences after the release ...
Design optimization studies indicate that a significant reduction in the size of the PCRV for a 2240...
The core concrete interaction (CCI) is an important phase of any severe accident where the reactor v...