New procedures for providing public notice concerning issuance of amendments to operating licenses.

The development and application of Kuosheng (BWR/6) nuclear power plant TRACE/SNAP model /
by: Shih, Chunkuan
Published: (2014)

Reactor vessel water level instrumentation in BWRS.
Published: (1984)

Anomalous behavior of recirculation loop plow in jet pump BWR plants.
Published: (1986)

The establishment and assessment of Chinshan (BWR/4) Nuclear Power Plant TRACE/SNAP model /
by: Wang, Jong-Rong
Published: (2014)

Assessment and management of ageing of major nuclear power plant components important to safety : BWR pressure vessels.
Published: (2005)

TRACE/SNAP model establishment of Chinshan nuclear power plant for ultimate response guideline /
by: Wang, Jong-Rong
Published: (2017)

TMI task action plan item I.G.1, "Special low power testing and training," recommendations for BWRS.
Published: (1983)

NRC staff review of the BWR owners' group (BWROG) control room survey program.
Published: (1983)

Inspections of BWR stainless steel piping.
Published: (1984)

Validation of the CHAN-component in TRACE using BWR full-size fine-mesh bundle tests /
by: Thieme, M.
Published: (2010)

BWR scram discharge system, clarification of diverse instrumentation requirement.
Published: (1981)

Service degradation of thick wall stainless steel recirculation system piping at a BWR plant.
Published: (1982)

The steam generating heavy water prototype reactor /
by: Firth, A.
Published: (1964)

Investigation on stability of a boiling heavy water reactor /
by: Nishihara, Hiroshi
Published: (1962)

Assessment and management of ageing of major nuclear power plant components important to safety : BWR pressure vessel internals.
Published: (2005)

BWR anticipated transients without scram in the MELLLA+ expanded operating domain /
by: Cheng, Lap-Yan
Published: (2015)

Failure of a boiling water reactor target rock main steam safety/relief valve.
Published: (2003)

Spurious system isolations caused by Panalarm model 86 thermocouple monitor.
Published: (1986)

Cracking in boiling-water-reactor Mark I and Mark II containments caused by failure of the inerting system.
Published: (1985)

BWR ECCS pump suction concerns following a LOCA /
by: Krotiuk, W. J.
Published: (2016)

Operational issues identified in boiling water reactor trip and transient.
Published: (2000)

Using TRACE, MELCOR, CFD, and FRAPTRAN to establish the analysis methodology for Chinshan Nuclear Power Plant spent fuel pool /
by: Wang, Jong-Rong
Published: (2018)

Cofrentes NPP (BWR/6) ATWS (MSIVC) analysis with TRAC-BF1 : 1D vs. point kinetics and containment response /
by: Escrivá, A.
Published: (2000)

IGSCC in BWR plants.
Published: (1984)

Intergranular stress corrosion cracking leading to steam generator tube failure.
Published: (1984)

The alternate mitigation strategies study of Chinshan BWR/4 by using the LOCA and SBO analysis of TRACE /
by: Wang, Jong-Rong
Published: (2014)

Status of NRC's staff review of BWRVIP-05.
Published: (1997)

ATWS analysis of Lungmen ABWR for MSIV closure transient /
by: Wang, Jong-Rong
Published: (2014)

Boiling water reactor safety/relief valve failures.
Published: (1983)

Scram discharge volume.
Published: (1980)

Higher than predicted erosion/corrosion in unisolable reactor coolant pressure boundary coolant inside containment at a boiling water reactor.
Published: (1992)

Degraded ability to isolate the reactor coolant system from low-pressure coolant systems in BWRS.
Published: (1986)

Failures to identify containment leakage due to inadequate local testing of BWR vacuum relief system valves.
Published: (1986)

Failures of scram discharge volume vent and drain valves.
Published: (1986)

Scram discharge volume designs.
Published: (1980)

Cracking of valves in the condensate return lines of a BWR emergency condensation system.
Published: (1992)