Published September 1985 | Version v1
Report Restricted

Pressurized thermal shock evaluation of the H.B. Robinson Unit 2 Nuclear Power Plant (Appendices A-K), Volume 2

Creators

Description

Supporting information is given with respect to: support system interaction analysis for H.B. Robinson Unit 2; PTS initiation-event frequency and branch probability screening estimates; a socio-technical approach to assessing human reliability (STAHR); quantification of operator actions; buoyancy effects in overcooling transients calculated for H.B. Robinson Unit 2; estimations of pressures, temperatures, and heat transfer coefficients for postulated overcooling sequences; the use of RTNDT and ΔRTNDT as independent variables; importance sampling methods in the OCA-P probabilistic fracture-mechanics analysis; useful results for the log-normal distribution; and responses to utility comments

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A99/MF A01 - GPO as TI86004578.

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Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
611 p.
Report number
NUREG/CR--4183-Vol.2

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
17062789
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
EVALUATION; HEAT TRANSFER; HUMAN FACTORS; HYDRAULICS; LOSS OF COOLANT; PRIMARY COOLANT CIRCUITS; REACTOR SAFETY; RISK ASSESSMENT; ROBINSON-2 REACTOR; THERMAL SHOCK; TRANSIENTS
Descriptors DEC
ACCIDENTS; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
ORNL/TM--9567/V2.