Overview Of The Activities In Spain On Irradiation Embrittlement Of Rpv Steel
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Author |
: A. Ballesteros |
Publisher |
: |
Total Pages |
: 8 |
Release |
: 1994 |
ISBN-10 |
: OCLC:1251668361 |
ISBN-13 |
: |
Rating |
: 4/5 (61 Downloads) |
Synopsis Overview of the Activities in Spain on Irradiation Embrittlement of RPV Steel by : A. Ballesteros
Specific problems such as the embrittlement of the WER reactors or the integrity evaluation of the Yankee Rowe reactor pressure vessel, show the necessity of continuing in the understanding of the mechanisms responsible for the embrittlement. Besides, in order to increase the safety and performance of the nuclear power plants, it is important to optimize the surveillance programmes and develop the mitigation techniques of the damage caused by neutron radiation.
Author |
: Harry Farrar |
Publisher |
: ASTM International |
Total Pages |
: 854 |
Release |
: 1994 |
ISBN-10 |
: 9780803118997 |
ISBN-13 |
: 0803118996 |
Rating |
: 4/5 (97 Downloads) |
Synopsis Reactor Dosimetry by : Harry Farrar
Proceedings of the 8th ASTM-Euratom Symposium, held in Vail, Colorado, Aug.-Sept. 1993, to provide a forum for experts to discuss their latest results under the broad theme of dosimetry for the correlation of radiation effects. Preceded by a summary of the keynote presentations and followed by summa
Author |
: P. Petrequin |
Publisher |
: |
Total Pages |
: 24 |
Release |
: 1983 |
ISBN-10 |
: OCLC:1251659608 |
ISBN-13 |
: |
Rating |
: 4/5 (08 Downloads) |
Synopsis Irradiation Embrittlement of Pressure Vessel Steels by : P. Petrequin
Research on irradiation embrittlement in modern pressure vessel steels was initiated at the French Atomic Energy Commission ten years ago. During this period many steels and welds were irradiated in the Triton and Siloe reactors; research was undertaken both independently and within the framework of research programs coordinated by the International Atomic Energy Agency.
Author |
: Lendell E. Steele |
Publisher |
: ASTM International |
Total Pages |
: 303 |
Release |
: 1986 |
ISBN-10 |
: 9780803104730 |
ISBN-13 |
: 0803104731 |
Rating |
: 4/5 (30 Downloads) |
Synopsis Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels by : Lendell E. Steele
Author |
: |
Publisher |
: |
Total Pages |
: 9 |
Release |
: 1982 |
ISBN-10 |
: OCLC:74674184 |
ISBN-13 |
: |
Rating |
: 4/5 (84 Downloads) |
Synopsis Investigation on the dependence of RPV steel embrittlement on irradiation temperature and neutron exposure by :
Author |
: J. R. Hawthorne |
Publisher |
: |
Total Pages |
: 40 |
Release |
: 1979 |
ISBN-10 |
: STANFORD:36105216450960 |
ISBN-13 |
: |
Rating |
: 4/5 (60 Downloads) |
Synopsis Survey of postirradiation heat treatment as a means to mitigate radiation embrittlement of reactor vessel steels by : J. R. Hawthorne
Author |
: DH. Njo |
Publisher |
: |
Total Pages |
: 22 |
Release |
: 1989 |
ISBN-10 |
: OCLC:1251643448 |
ISBN-13 |
: |
Rating |
: 4/5 (48 Downloads) |
Synopsis The Swiss Research Program on Irradiation Embrittlement and Annealing of Reactor Pressure Vessel Steels by : DH. Njo
The present research program on irradiation embrittlement and annealing of reactor pressure vessel (RPV) steels in Switzerland is carried out at the Paul Scherrer Institute for Reactor Research. The particular program structure and its relation to the concept for an improved surveillance program is described.
Author |
: |
Publisher |
: |
Total Pages |
: |
Release |
: 1986 |
ISBN-10 |
: OCLC:834702859 |
ISBN-13 |
: |
Rating |
: 4/5 (59 Downloads) |
Synopsis Radiation embrittlement of nuclear reactor pressure vessel steels by :
Author |
: Martin L. Grossbeck |
Publisher |
: ASTM International |
Total Pages |
: 767 |
Release |
: 2004 |
ISBN-10 |
: 9780803134775 |
ISBN-13 |
: 0803134770 |
Rating |
: 4/5 (75 Downloads) |
Synopsis Effects of Radiation on Materials by : Martin L. Grossbeck
Author |
: AV. Nikolaeva |
Publisher |
: |
Total Pages |
: 11 |
Release |
: 2000 |
ISBN-10 |
: OCLC:1251647893 |
ISBN-13 |
: |
Rating |
: 4/5 (93 Downloads) |
Synopsis Application of the Floating Curve Model for Estimation of Re-Irradiation Embrittlement of VVER-440 RPV Steels by : AV. Nikolaeva
Radiation embrittlement and its mitigation by annealing of VVER-440 reactor pressure vessel steels are studied. The Russian regulatory approach for prediction of radiation embrittlement of VVER-440 steels is considered. Results of an investigation of materials cut out of operating nuclear power plants are discussed. Different models of re-irradiation embrittlement are compared. A new model for assessment of embrittlement under re-irradiation is developed.