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| 1 | Treatment of pseudotumor cerebri with Diamox ( aeetazolamide )显示文摘 | Tomsak RL Niffenegger AS Remler BF | 1988 | J Clin Neuroophthahnol1988，8，： | 1 |
| 2 | Integrity analysis of a reactor pressure vessel subjected to pressurized thermal shocks by considering constraint effect显示文摘 | Qian G Niffenegger M | 2013 | Engineering Fracture Mechanics2013，，： | 1 |
| 3 | BEST-SELLER-The Time Traveler's Wife显示文摘 | AUDREY NIFFENEGGER | 2010 | China's Foreign Trade2010，，2： | 1 |
| 4 | Procedures, methods and computer codes for the probabilistic assessment of reactor pressure vessels subjected to pressurized thermal shocks 显示文摘 | Qian G Niffenegger M | 2013 | Nuclear Engineering and Design2013，258，： | 1 |
| 5 | Treatment of pseudotumor cerebri with Diamox(acetazolamide)显示文摘 | Tomsak RL Niffenegger AS Remler BF | 1988 | J Clin Neuroophthalmol1988，8，： | 1 |
| 6 | Monitoring Fa tigue Degradation in Austenitie Stainless Steels显示文摘 | Kalkhof D Grosse M Niffenegger M | | 0，，： | 1 |
| 7 | A computational fatigue analysis of cyclic thermal shock in notched specimens显示文摘 | Janssens K G F Niffenegger M Reichlin K | 2009 | Nuclear Engineering and Design2009，239，1： | 1 |
| 8 | Procedures, methods and computer codes for the probabilistic assessment of reactor pressure vessels subjected to pressurized thermal shocks显示文摘 | QIAN G NIFFENEGGER M | 2013 | Nuclear Engineering and Design2013，258，： | 1 |
| 9 | Monitoring the embrittlement of reactor pressure vessel steels by using the Seeheck eoeffieient显示文摘 | NIFFENEGGER M LEBER H | 2009 | J Nucl Mater2009，389，1： | 1 |
| 10 | Probabilistic assessment of a reactor pressure vessel subjected to pressurized thermal shocks by using crack distributions显示文摘 | QIAN G GONZ h LEZ-ALBUIXECH V F NIFFENEGGER M | 2014 | Nuclear Engineering and Design2014，270，： | 1 |
| 11 | Probabilistic fracture assessment of piping systems based on FITNET FFS procedure显示文摘 | QIAN G NIFFENEGGER M | 2011 | Nuclear Engineering and Design2011，241，3： | 1 |
| 12 | Sensitivity of magnetiza-tion curves of different austenitic stainless tube andpipe steels to mechanical fatigue显示文摘 | Niffenegger M Leber H J | 2008 | Journal of Nucle-ar Materials2008，377，： | 1 |
| 13 | Phosphine fumigation of flue-cured tobacco warehouses for the control of the cigarette beetle显示文摘 | Childs D P Overby J E Niffenegger D | 1969 | Tobacco Sci1969，168，21： | 1 |
| 14 | Procedures, methods and computer codes for the probabilistic assessment of reactor pressure vessels subjected to pressurized thermal shocks显示文摘 | Guian Qian Markus Niffenegger | 2013 | Nuclear Engineering and Design2013，，： | 1 |
| 15 | Probabilistic assessment of a reactor pressure vessel subjected to pressurized thermal shocks by using crack distributions显示文摘 | QIAN G GONZ kLEZ-ALBUIXECH V F NIFFENEGGER M | 2014 | Nuclear Engineering and Design2014，270，： | 1 |
| 16 | Procedures, methods and computer codes for the probabilistic assessment of reactor pressure vessels subjected to pressurized thermal shocks显示文摘 | QIAN G NIFFENEGGER M | 2013 | Nuclear Engineering and Design2013，258，： | 1 |
| 17 | Monitoring of low-cycle fatigue degradation in X6CrNiTi18-10 austenitic steel 显示文摘 | GROSSE M NIFFENEGGER M KALKHOF D | 2001 | Journal of Nuclear Materials2001，296，： | 1 |
| 18 | Influen- cing parameters on martensite transformation during low cycle fa- tigue for steel AISI 321显示文摘 | GROSSE M KALKHOF D NIFFENEGGER M | 2006 | Materials Science and Engineering: A2006，437，1： | 1 |
| 19 | 时间旅行者的妻子显示文摘克莱尔:被人抛下真的不好受。我等着亨利,并不知道他在哪儿,只想知道他还好吗。独守在这里真的不好受。
我让自己忙起来,这样时间就过得快一点。 | Audrey Niffenegger 王建刚(译) | 2010 | 英语广场(美丽英文)2010，，1： | 0 |
| 20 | 反应堆压力容器承压热冲击概率评价法的规范、方法及计算程序显示文摘反应堆压力容器(RPV)是轻水堆最重要的一道安全屏障,其工作于高温环境下,并承受着强中子辐照,因此容易产生脆化现象。对于压水堆而言,RPV完整性的一个潜在的威胁是承压热冲击工况(PTS)。因此,在评价RPV的完整性时需要考虑中子辐照效应。本文讨论了承压热冲击工况下RPV完整性的分析规范和方法。简要介绍了FAVOR和PASCAL两个广泛应用于RPV承压热冲击分析的计算机程序,并对其进行了比较。通过一个基准案例展示了使用FAVOR程序开展完整性分析的规范和方法,讨论了热预应力(WPS)、断裂韧性和约束效应对于RPV完整性的影响。由于Master曲线法比ASME给出的模型更接近实际情况,因此推荐使用该方法。为了将测试样品的数据转换为RPV的断裂韧性数据,使用了基于局部断裂力学法的概率论方法。 | Guiana Qian Markus Niffenegger | 2014 | 国外核动力2014，35，1： | 0 |
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