Stopienie rdzenia reaktora jądrowego (Polish Wikipedia)

Analysis of information sources in references of the Wikipedia article "Stopienie rdzenia reaktora jądrowego" in Polish language version.

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15iaea.org

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aps.org

journals.aps.org

Richard Wilson, Kamal J. Araj, Augustine O. Allen, Peter Auer, David G. Boulware, Fred Finlayson, Simon Goren, Clark Ice, Leon Lidofsky, Allen Lee Sessoms, Mary L. Shoaf, Irving Spiewak, Thomas Tombrello, Herbert S. Gutowsky, Andreas Acrivos, Herman Feshbach, and William A. Fowler (APS Study Group Participants, APS Council Review Committee). Report to The American Physical Society of the study group on radionuclide release from severe accidents at nuclear power plants. „Reviews of Modern Physics”. 57 (3), s. S1-S144, 1985. DOI: 10.1103/RevModPhys.57.S1.

books.google.com

4.6.1 Design Basis Accident for the AGR: Depressurization Fault. W: Geoffrey Frederick Hewitt: Introduction to nuclear power. Collier, John Gordon. Londyn: Taylor & Francis, 2000, s. 133. ISBN 978-1-56032-454-6. [dostęp 2010-06-05]. (ang.).

doe.gov

id.doe.gov

Idaho National Engineering and Environmental Laboratory: Test Area North Fact Sheet. [dostęp 2011-04-08]. (ang.).
SL-1 Reactor Accident on January 3, 1961, Interim Report. Windsor: U.S. Atomic Energy Commision, 1961. [dostęp 2011-06-14]. (ang.).

doi.org

Richard Wilson, Kamal J. Araj, Augustine O. Allen, Peter Auer, David G. Boulware, Fred Finlayson, Simon Goren, Clark Ice, Leon Lidofsky, Allen Lee Sessoms, Mary L. Shoaf, Irving Spiewak, Thomas Tombrello, Herbert S. Gutowsky, Andreas Acrivos, Herman Feshbach, and William A. Fowler (APS Study Group Participants, APS Council Review Committee). Report to The American Physical Society of the study group on radionuclide release from severe accidents at nuclear power plants. „Reviews of Modern Physics”. 57 (3), s. S1-S144, 1985. DOI: 10.1103/RevModPhys.57.S1.

energy.gov

etec.energy.gov

R.S. Hart: Distribution of fission product contamination in the SRE. Canoga Park: Atomic International, 1962. [dostęp 2011-06-14]. (ang.).

iaea.org

3. Afterheat removal in modular gas-cooled reactors. W: International Atomic Energy Agency: Heat transport and afterheat removal for gas cooled reactors under accident conditions. Wiedeń: IAEA, 2000, seria: IAEA-TECDOC-1163. [dostęp 2010-06-21]. (ang.).
Safety considerations concerning nuclear power plants associated with process heat and/or hydrogen production. W: IAEA-TECDOC-1085: Hydrogen as an energy carrier and its production by nuclear power. Wiedeń: IAEA, 1999. [dostęp 2011-04-30]. (ang.).
T. Okkonen, T.N. Dinh, T.N. Bui, B.R. Sehgal: Quantification of the Ex-vessel Severe Accident Risks for the Swedish Boiling Water Reactors – A Scoping Study Performed for the APRI Project. Stockholm: Norstedts Tryckeri AB, 1997, seria: SKI Project Number 94403. ISSN 1104-1374. [dostęp 2011-05-05]. (ang.).
A. Birkhofer. The German Risk Study for Nuclear Power Plants. „IAEA Bulletin”. 22 (5/6). Wiedeń: IAEA. [dostęp 2017-01-07]. (pol.).
A.M.J.M. Van Heel: In-vessel core retention through external flooding of the reactor pressure vessel. Petten: Netherlands Energy Research Foundation, 1995. [dostęp 2011-04-30]. (ang.).
Pierre Tanguy. Three decades of nuclear safety. „IAEA BULLETIN”, s. 53, 1988. Wiedeń: IAEA. [dostęp 2011-04-30]. (ang.).
David D. Yue, W.A. Condon: Severe-accident-sequence assessment of hypothetical complete-station blackout at the Browns Ferry Nuclear Plant. Port Chester: U.S. Nuclear Regulatory Commission, 1981. [dostęp 2011-05-11]. (ang.).
CARNSORE: Hypothetical Reactor Accident Study. O. Walmod-Larsen, N.O. Jensen, L. Kristensen, A. Meide, K.L. Nedergård, F. Nielsen, E. Lundtang Petersen, T. Petersen, S. Thykier-Nielsen. Roskilde: Risø National Laboratory, 06 1984, seria: R-427. ISBN 87-550-1170-5. [dostęp 2011-05-04]. (ang.).
E.A.G Larson: A general description of the NRX reactor. Chalk River: Atomic Energy of Canada Limited, 1961, s. 38, seria: AECL-1377. [dostęp 2011-06-14]. (ang.).
John Horan, Julie Braun: Occupational radiation exposure history of Idaho Field Office Operations at the INEL. Idaho: Idano National Engineering Laboratory, 1993, s. 38, seria: EGG-CS-11143. [dostęp 2011-06-14]. (ang.).
Ole Reistad, Povl L. Ølgaard: Inventory and source term evaluation of russian nuclear power plants for marine applications. Roskilde: Nordisk kernesikkerhedsforskning, 2006, seria: NKS-139. ISBN 87-7893-201-7. [dostęp 2011-05-02]. (ang.).
4. Troubles with the fast breeder reactors (1986 – 1992). W: Jean-François Sauvage: Phènix – 30 years of history: the heart of a reactor. EdF, 2004. ISBN 87-7893-201-7. [dostęp 2011-05-02]. (ang.).
Cleanup and decommissioning of nuclear reactor after a severe accident. Wiedeń: IAEA, 1992, seria: Technical reports series no. 346. [dostęp 2011-06-16]. (ang.).

www-pub.iaea.org

P.C. Minshall, A.J. Wickham: The description of Wigner energy and its release from Windscale pile graphite for application to waste packaging and disposal. Berkeley: BNFL Magnox Generation, Berkeley Center. [dostęp 2011-06-14]. (ang.).

www-ns.iaea.org

IAEA: Nuclear Accidents. [dostęp 2011-05-02]. (ang.).

inl.gov

SCDAP/RELAP5-3D. [dostęp 2011-06-23]. (ang.).

nrc.gov

Perspectives on Reactor Safety (NUREG/CR-6042) (Reactor Safety Course R-800). Haskin, F.E.; Camp, A.L.. Wyd. 1. Beltsville, MD: U.S. Nuclear Regulatory Commission, 1994, s. 3.1–5. [dostęp 2010-11-23]. (ang.).
Perspectives on Reactor Safety (NUREG/CR-6042) (Reactor Safety Course R-800), 1st Edition. Haskin, F.E.; Camp, A.L.. Beltsville, MD: U.S. Nuclear Regulatory Commission, 1994, s. 3.5–1 – 3.5–4. [dostęp 2010-12-24]. (ang.).
Perspectives on Reactor Safety (NUREG/CR-6042) (Reactor Safety Course R-800), 1st Edition. Haskin, F.E.; Camp, A.L.. Beltsville, MD: U.S. Nuclear Regulatory Commission, 1994, s. 3.5–4 – 3.5–5. [dostęp 2010-12-24].
NRC research activities: computer codes. [dostęp 2011-06-23]. (ang.).

nytimes.com

Andrew E. Kramer: Nuclear Industry in Russia Sells Safety, Taught by Chernobyl. 2011-03-22, 2011-04-08. [dostęp 2011-04-08]. (ang.).

oecd-nea.org

K. Trambauer, T.J. Haste, B. Adroguer, Z. Hózer, D. Magallon: In-vessel core degradation code validation matrix: update 1996-1999. Zurita A.. Saint-Germain: OECD Nuclear Energy Agency, 10 2000, s. 30–81. [dostęp 2011-06-23]. (ang.).

osti.gov

P. Kuan: Managing water addition to a degraded core. Hanson, D.J., Odar, F.. 1991. [dostęp 2010-11-22]. (ang.).
Ronald R.R.R. Bellamy Ronald R.R.R., Investigations into the air cleaning aspects of the Three Mile Island accident, Melvin W.M.W. First (red.), „Proceedings of the 16th DOE Nuclear Air Cleaning Conference, 20–23 October 1980”, 2, San Diego: US Department of Energy, 1981, s. 1427–1441 [dostęp 2022-12-06] (ang.).
Stephen A. Hodge: Thermalhydraulic processes in the reactor coolant system of a BWR under severe accident conditions. Oak Ridge National Laboratory for Department of Energy. (ang.).

si.edu

americanhistory.si.edu

Smithsonian Museum: Three Mile Island: The Inside Story. [dostęp 2011-06-22]. (ang.).

slideshare.net

Summary of reactor status on 31st of May 2011 by Javier Yllera – IAEA.

spb.org.ru

Thomas Nilsen, Igor Kudrik, Alexandr Nikitin: The Russian Northern Fleet Nuclear submarine accidents. Bellona, 1996. [dostęp 2011-05-02]. (ang.).

web.archive.org

Michael Young: Hazardous Duty. Naval Officers’ Association of Canada, 2007. [dostęp 2011-05-02]. (ang.).

worldcat.org

T. Okkonen, T.N. Dinh, T.N. Bui, B.R. Sehgal: Quantification of the Ex-vessel Severe Accident Risks for the Swedish Boiling Water Reactors – A Scoping Study Performed for the APRI Project. Stockholm: Norstedts Tryckeri AB, 1997, seria: SKI Project Number 94403. ISSN 1104-1374. [dostęp 2011-05-05]. (ang.).
JerzyJ. Sobkowski JerzyJ., Chemia radiacyjna i ochrona radiologiczna, Warszawa: Adamantan, 2009, s. 99, ISBN 978-83-7350-135-5, OCLC 750998176 .
M.G. Plys. Hydrogen production and combustion in severe reactor accidents: An integral assesment perspective. „Nuclear Technology”. 101 (3), s. 400–410, 1993. American Nuclear Society. ISSN 0029-5450.