| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Analysis of containment venting at the peach bottom atomic power station
|
Hanson, D.J.
|
|
1988
|
108 |
1-2 |
p. 71-81
11 p.
|
artikel
|
| 2 |
Analysis results from the Los Alamos 2D/3D program
|
Boyack, B.E.
|
|
1988
|
108 |
1-2 |
p. 265-271
7 p.
|
artikel
|
| 3 |
Application of engineering and multi-dimensional finite difference codes to HDR thermal mixing experiments TEMB
|
Wolf, L.
|
|
1988
|
108 |
1-2 |
p. 137-165
29 p.
|
artikel
|
| 4 |
BWR pipe crack remedies evaluation
|
Shack, W.J
|
|
1988
|
108 |
1-2 |
p. 199-210
12 p.
|
artikel
|
| 5 |
Containment venting as a mitigation technique for BWR MARK I plant ATWS
|
Harrington, R.M.
|
|
1988
|
108 |
1-2 |
p. 55-69
15 p.
|
artikel
|
| 6 |
CSNI validation matrix for PWR and BWR thermal-hydraulic system codes
|
Wolfert, K.
|
|
1988
|
108 |
1-2 |
p. 107-119
13 p.
|
artikel
|
| 7 |
Dynamic load effects on gate valve operability and snubber performance
|
Steele Jr., Robert
|
|
1988
|
108 |
1-2 |
p. 15-21
7 p.
|
artikel
|
| 8 |
Editorial Board
|
|
|
1988
|
108 |
1-2 |
p. iii-vii
nvt p.
|
artikel
|
| 9 |
Flaw density examinations of a clad boiling water reactor pressure vessel segment
|
Cook, K.V.
|
|
1988
|
108 |
1-2 |
p. 211-219
9 p.
|
artikel
|
| 10 |
Fluence-rate effects on irradiation embrittlement and composition and temperature effects on annealing/reirradiation sensitivity
|
Hawthorne, J.R.
|
|
1988
|
108 |
1-2 |
p. 221-232
12 p.
|
artikel
|
| 11 |
Functionality and leak integrity of containment penetration systems subjected to design basis dynamic loads
|
Steele Jr., Robert
|
|
1988
|
108 |
1-2 |
p. 7-13
7 p.
|
artikel
|
| 12 |
HDR phase II vibrational experiments
|
Malcher, L.
|
|
1988
|
108 |
1-2 |
p. 23-36
14 p.
|
artikel
|
| 13 |
Overview of recent operating experience regarding plant aging
|
Holahan, Gary M.
|
|
1988
|
108 |
1-2 |
p. 187-198
12 p.
|
artikel
|
| 14 |
Phenomenological studies on molten core-concrete interactions
|
Greene, G.A.
|
|
1988
|
108 |
1-2 |
p. 167-177
11 p.
|
artikel
|
| 15 |
Physical model for reactor coolant pumps
|
Schneider, K.
|
|
1988
|
108 |
1-2 |
p. 99-105
7 p.
|
artikel
|
| 16 |
Preface
|
Kussmaul, K.
|
|
1988
|
108 |
1-2 |
p. ix-x
nvt p.
|
artikel
|
| 17 |
Risk evaluations of aging phenomena: The linear aging reliability model and its extensions
|
Vesely, W.E.
|
|
1988
|
108 |
1-2 |
p. 179-185
7 p.
|
artikel
|
| 18 |
SCTF-III test plan and recent SCTF-III test results
|
Iguchi, Tadahi
|
|
1988
|
108 |
1-2 |
p. 241-247
7 p.
|
artikel
|
| 19 |
Steam separator modeling for various nuclear reactor transients
|
Paik, C.Y.
|
|
1988
|
108 |
1-2 |
p. 83-97
15 p.
|
artikel
|
| 20 |
Summary of CCTF test results - assessment of current safety evaluation analysis on reflood behavior during a LOCA in a PWR with cold-leg-injection-type ECCS
|
Iguchi, Tadashi
|
|
1988
|
108 |
1-2 |
p. 233-239
7 p.
|
artikel
|
| 21 |
Tests of the TRAC code against known analytical solutions for stratified flow
|
Black, P.S.
|
|
1988
|
108 |
1-2 |
p. 121-136
16 p.
|
artikel
|
| 22 |
The need for further nuclear safety research: A present French view
|
Bussac, Jean
|
|
1988
|
108 |
1-2 |
p. 1-5
5 p.
|
artikel
|
| 23 |
The results of 5% small-break LOCA tests and natural circulation tests at the ROSA-IV LSTF
|
Tasaka, K.
|
|
1988
|
108 |
1-2 |
p. 37-44
8 p.
|
artikel
|
| 24 |
TMI-2 accident scenario update
|
Tolman, E.L.
|
|
1988
|
108 |
1-2 |
p. 45-54
10 p.
|
artikel
|
| 25 |
UPTF test results: First three separate effect tests
|
Weiss, P.A.
|
|
1988
|
108 |
1-2 |
p. 249-263
15 p.
|
artikel
|
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