This work reviews proposed safety criteria prepared by the German Bundesministerium des Innern (BMI) for future licensing of gas-cooled high-temperature reactor (HTR) concepts in the Federal Republic of Germany. Comparison is made with US General Design Criteria (GDCs) in 10CFR50 Appendix A and with German light water reactor (LWR) criteria. Implications for the HTR design relative to the US design and safety approach are indicated. Both inherent characteristics and design features of the steam cycle, gas turbine, and process heat concepts are taken into account as well as generic design options such as a pebble bed or prismatic core
The purpose of this document is to present a safety plan as part of an overall program plan for the ...
The Swedish AB Atomenergi held a HTR Information Seminar in Stockholm on January 11, 1978. At this s...
The high-temperature gas-cooled nuclear reactors (HTGRs) technology was developed in the 1960s and 1...
The purpose of this document is to provide an initial, focused reference to the safety characteristi...
For more than 50 years the pebble-bed High Temperature Reactor (HTR) has been under development in G...
According to its inherent safety the Pebble Bed High Temperature Reactor is suitable for the product...
Current interest expressed by industry in HTGR plants, particularly modular plants with power up to ...
The project supported the Nuclear Regulatory Commission (NRC) in identifying and evaluating the regu...
The inherent properties of a High-Temperature Gas-cooled Reactor (HTGR) facilitate the design of the...
The present trend analysis is an attempt at assessing the risk caused by incidents and accidents for...
The report deals with two special questions for gas-cooled high-temperature reactors of modular desi...
The present estimation of the HTR 500 design concept attempts to filter the risk-relevant accidents ...
International audienceA comparison of 3 Generation IV reactor concepts between them and with a PWR o...
International audienceA comparison of 3 Generation IV reactor concepts between them and with a PWR o...
The Next Generation Nuclear Plant (NGNP) will be a licensed commercial high temperature gas-cooled r...
The purpose of this document is to present a safety plan as part of an overall program plan for the ...
The Swedish AB Atomenergi held a HTR Information Seminar in Stockholm on January 11, 1978. At this s...
The high-temperature gas-cooled nuclear reactors (HTGRs) technology was developed in the 1960s and 1...
The purpose of this document is to provide an initial, focused reference to the safety characteristi...
For more than 50 years the pebble-bed High Temperature Reactor (HTR) has been under development in G...
According to its inherent safety the Pebble Bed High Temperature Reactor is suitable for the product...
Current interest expressed by industry in HTGR plants, particularly modular plants with power up to ...
The project supported the Nuclear Regulatory Commission (NRC) in identifying and evaluating the regu...
The inherent properties of a High-Temperature Gas-cooled Reactor (HTGR) facilitate the design of the...
The present trend analysis is an attempt at assessing the risk caused by incidents and accidents for...
The report deals with two special questions for gas-cooled high-temperature reactors of modular desi...
The present estimation of the HTR 500 design concept attempts to filter the risk-relevant accidents ...
International audienceA comparison of 3 Generation IV reactor concepts between them and with a PWR o...
International audienceA comparison of 3 Generation IV reactor concepts between them and with a PWR o...
The Next Generation Nuclear Plant (NGNP) will be a licensed commercial high temperature gas-cooled r...
The purpose of this document is to present a safety plan as part of an overall program plan for the ...
The Swedish AB Atomenergi held a HTR Information Seminar in Stockholm on January 11, 1978. At this s...
The high-temperature gas-cooled nuclear reactors (HTGRs) technology was developed in the 1960s and 1...