-
1.1.
原子核、核子及相关术语
质子
proton
中子
neutron
电子
electron
核子
nucleon
核
nucleus
(
pl.
)
nuclei
原子
atom
光子
photon
正电子
positron
量子
quantum, quanta (pl.)
电子伏特
electron-
volt (eV)
1.2.
相关元素与材料
1.2.1.
核燃料与增殖材料
铀
uranium
< br>(
U
)
钚
plutonium
(
Pu
)
氘,重氢
deuterium
,
heavy
hydrogen
氚
tritium
混
合
氧
化
物
燃
料
(
MOX
燃
料
)
Mixed
(Uranium and Plutonium) OXide fuel
二氧化铀
uranium
dioxide
浓缩铀
enriched uranium
贫铀
depleted
uranium
1.2.2.
其它核材料及核电厂用材料
慢化剂
moderator
轻水
light water
重水
heavy water
石墨
graphite
冷却剂
coolant
氦
helium
液态金属
liquid metal
钠
sodium
包壳
cladding
铝
aluminium
镁
magnesium
锆
zirconium
兆电子伏特
mega electron-volt (MeV)
同位素
isotope
原子序数
atomic
number
质量数
mass
number
超铀元素
transuranium element
元素周期表
periodic
table
热中子
thermal
neutron
快中子
fast
neutron
复合核
compound nucleus
碳化铀
uranium carbide
钍
thorium
锂
lithium
锕系元素
actinide element
易裂变的
fissile
可裂变的、可裂变物质
fissionable
增殖同位素
fertile
isotope
核嬗变
nuclear transmutation
转化
conversion
锆
2/4
合金
zircaloy-2/4
不锈钢
stainless steel
控制材料
control
material
通量展平
flux-shaping
银
silver
铟
indium
镉
cadmium
可燃毒物
burnable
poison
硼
boron
硼酸
boric acid
锂
lithium
铍
beryllium
1
乏燃料
spent fuel
因科镍,因康
INCONEL
不锈钢
stainless
steel
1.3.
核反应及相关术语
decay
衰变
fission
裂变
fusion
聚变
nuclear
reaction
核反应
chain
reaction
链式反应
cross section
截面
microscopic cross
section
微观截面
macroscopic cross
section
宏观截面
absorbing cross
section
吸收截面
scattering cross
section
散射截面
barn
靶恩
delayed
neutron
缓发中子
prompt
neutron
瞬发中子
prompt
criticality
瞬发临界
fissile
易裂变的
fissionab
可裂变的
le
morderate / slow
down
慢化
breeding
ratio
增殖比
burnup
燃耗
reactivity
反应性
neutron cycle
中子循环
fission
product
裂变产物
criticality
临界
prompt
critical
瞬发临界
flux
通量
xenon
氙
iodine
碘
actinide
锕系(元素)
reactivity
worth
反应性价值
慢
化
剂
温
度
系
数
moderator
temperature
coefficient
反应性系数
reactivity
coefficient
剩余反应性
excess
reactivity
燃料比功率
fuel
specific
power
倍增因子
multiplication factor
有
效
增
殖
系
数
effective
multiplication
factor
;
effective
multiplication constant
无
p>
限
介
质
增
殖系
数
infinite
multiplication
factor
;
infinite multiplication constant
快中子增殖系数
fast fission factor
热
中
子
利
用
系
数
thermal
utilization
factor
不泄漏几率
nonleakage
probability
逃
脱
共
振
俘
获
几
率
resonance
escape
probability
四因子公式
four-factor
formula
多普勒增宽
Doppler broadening
*
< br>总集成中子通
量
/
总积分中
p>
子通量
Total
Integrated
Neutron
Flux
=
Integrated
Flux
or
Fluence
(
注量
) = Neutron density
?
V
elocity
?
Time [
单位:
n/m
3
?
m/s
?
s =
n/m
2
]
1.4.
反应堆
压水堆
Pressurized
Water Reactor (PWR)
沸水堆
Boiling Water Reactor (BWR)
加拿大重水铀
反应堆(坎
杜堆)
CAN
adian
Deuterium
and
Uranium
reactor
(CANDU)
/
pressurized heavy water reactor (PHWR)
英国气冷堆(美诺克斯堆)
British gas-
cooled Magnox reactor
2
高温气冷堆
high
temperature gas-cooled reactor (HTGR)
快中子增殖反应堆
fast
breeder reactor (FBR)
轻水堆
Light Water Reactor (LWR)
先进反应堆
advanced
reactor
超临界水反应堆
supercritical water reactor
欧洲压水堆(第三代反应堆之一)
European Pressurized water Reactor
(EPR)
(美国)先进压水堆
600/1000
(第三代
(+)
反应堆之一)
AP(WR)600 / 1000
1.5.
核电厂部件、设备与系统
燃料芯块
fuel pellet
燃料元件
fuel element
燃料棒
fuel rod
燃料组件
fuel assembly
定位格架
spacer grid
法兰
flange
密封环
seal ring
阻力塞
plug
< br>(
上
/
下
)
腔室
(upper /
lower ) plenum
堆芯,活性区
core
反
应
堆
压
力容
器
Reactor
Pressure
V
essel
(RPV)
上封头
upper closure head
液
< br>压
螺
栓
拉
伸
机
(
张
紧
机
)
hydraulic
stud
tensioner
包覆层
clad
(
碳钢表面的防腐蚀堆焊层
)
控制棒
control rod <
/p>
控
制
棒
组
件
Control
Element
Assembly
(CEA)
可燃吸收棒
burnable absorber rod
控
制
棒
驱
动
机
构
Control
Element
Drive
Mechanism (CEDM)
变送器
transmitter
信号调理
signal
regulation
吊篮
barrel
进
/
出口接管
inlet / outlet nozzle
冷
/
热端,冷
/
热腿,冷<
/p>
/
热管段
cold / hot leg
反应堆堆内构件
reactor
vessel internals
肿胀
swelling
腐蚀
corrode, corrosion
3
侵蚀
erode, erosion
氧化
oxidation, oxidize
完整性
integrity
反应堆冷却剂泵(主泵)
Reactor
Coolant
Pump (RCP)
屏蔽泵
canned (motor) pump
轴封泵
shaft seal
pump
反应堆冷却剂系统(一回路系统)
Reactor
Coolant System (RCS)
核
蒸
汽
供
应
< br>系
统
Nuclear
Steam
Supply
System (NSSS)
一回路
primary loop/circuit
一回路系统
p>
/
主回路系统
primary system
二回路
secondary
loop
稳压器
pressurizer (PRZ)
波动管
surge line
汽水分离器
moisture
separator
干燥器(二
/
三
级汽水分离器)
steam dryer
安全阀
safety valve
卸压阀
relief valve
溢流阀
overflow
valve
主蒸汽隔离阀
main
steam isolation valve
单向阀
check valve
止回阀
non-return
valve
主蒸汽联箱
main
steam header
给水调节阀
feed
regulating valve
蒸汽发生器
Steam Generator (SG)
主蒸汽管
Main Steam
Line (MSL)
汽轮机
steam turbine
汽
水<
/p>
分
离
再
热
器
Moisture
Separator
Reheater (MSR)
给水泵
feed (water)
pump
上充泵
charging
pump
凝汽器
condenser
发电机
(electric) generator
安全壳
containment
地基,基础
foundation
烟道
stack
贯穿件
penetration
核岛
nuclear island
常规岛
conventional
island
核电厂配套子项
Balance of Plant (BOP)
一
回
路
辅
助
系
统
auxiliary
system
for
primary loop
化学与容积控制系统
(化容系统)
Chemical
and
V
olume Control System (CVCS)
专
设
安
全
设
施
Engineered
Safety
Feature
(ESF)
余
热
排
出
系
统
Residual
Heat-Removal
System (RHRS)
应急堆芯冷却系统
Emergency Core Cooling
System (ECCS),
安注系统
Safety Injection (SI)
System
直接注射系统
direct vessel injection (DVI)
换
料
水
箱
Refueling
Water
Storage
Tank
(IRWST)
(
乏
)
燃料贮存水池
(spent) fuel storage pool
燃料装卸系统
fuel
handling system
蓄压箱
accumulator
机组
unit
辅助喷淋
auxiliary spray
柴油发电机
Diesel
generator
自动保护系统
Automatic
Protective
System
(APS)
自
动
降
压
系
统
automatic
depressurization
system
(ADS)
仪
控
系
< br>统
Instrumentation
and
Control
System (I & C system)
开关设备,开关柜
switch
gear
蒸汽轴封系统,压盖蒸汽密封系统
gland
steam system
汽轮机旁路管
turbine
bypass line
辅助给水泵
auxiliary
feedwater pump
汽动给水泵
turbine driven feedwater pump
导管
conduit
冷凝水泵
condensate pump
冷凝水增压泵
condensate booster pump
水润滑轴承
water
lubricated bearing
人孔
man way
检修孔
accessory
port
1.6.
反应堆运行
运行
operation
运行工况
operating
condition
操纵员
operator
维护
maintenance
监督、监视
surveillance
监督试样
surveillance specimen
辐照监督管
irradiation
surveillance capsule
辐
照
监
督
试
样
盒
surveillance
specimen
compartment
4
硼浓度
boron concentration
稀释
dilution /
dilute
硼注入
boron
injection
停堆
shutdown
紧急停堆
scram / trip
停役
outage
换
料
< br>停
堆
refueling
outage
/
refueling
shutdown
换料
refuel
卸料
discharge
倒料
shuffling
满功率运行
full power
operation
负荷跟踪
load following
甩负荷
load
shedding, load rejection
(
控制
棒等的
)
插入
insertion
(
控制棒等的<
/p>
)
抽出
withdrawal
反应堆调节系统
Reactor
Regulating
System
(RRS)
(
蒸汽发生器
)
排污、下泄
blowdown
规程
procedure
技术规格
technical specification
瞬态,瞬变
transient
安装调试
installation
and commissioning
冷态试验
cold
functional
test
热态试验
hot
functional
test
(
反应堆
)
启动试验
(reactor) start up test
退役
decommissioning
主控室
main control
room
方位角偏差
azimuthal tilt
径向功率分布
radial
power distribution
轴向功率分布
axial
power distribution
燃料管理方案
fuel management scheme
燃
料
-
包
p>
壳
交
互
作
用
fuel-clad
interaction
effect
芯
块
-
包
壳
交
互
作
用<
/p>
(PCI)
pellet-clad
interaction
(
燃料
p>
)
栅格、晶格
lattice
1.7.
反应堆安全
核安全
nuclear
safety
安全功能
safety
function
衰变热
decay heat
余热
residual heat
空泡系数
void
coefficient
法律
law
法规
regulation / code
联邦管理法规
Code
of
Federal
Regulations
(CFR)
法案(美)
Act
导则
guidance
安全
1/2/3
级
saf
ety class 1/2/3
可靠性
reliability
容限,裕量,边界
margin
堆芯热裕量
core thermal margin
堵管裕量
tube
plugging margin
运行安全裕量
operating margin
标准,准则
criterion
,复数形式
:
criteria
概率安全分析
Probabilistic
Safety
Analysis
(PSA)
概率风险
分析
Probabilistic
Risk
Analysis
(PRA)
确<
/p>
定
论
安
全
分
析
deterministic
safety
5
analysis
初
步
安
全
分
析
报
告
Preliminary
Safety
Analysis Report (PSAR)
最终安
p>
全分
析报
告
Final
Safety
Analysis
Report (FSAR)
安全评价报告
safety
evaluation report
事件
incident
事故
accident
后果
consequence
严重事故
severe accident
堆芯损毁
core damage
堆芯融化
core
meltdown
全厂断电
station blackout
冷却剂丧失事故
(失水事故)
Loss-of-coolant
Accident (LOCA)
反
应
性
引
入
事<
/p>
故
Reactivity
Insertion
Accident (RIA)
未
能
紧
急
停
堆
的
预
计
瞬
变
Anticipated
Transient
Without Scram (A
TWS)
失电
Loss of Power
失流
Loss of flow
先漏后破
leak before break (LBB)
故障安全,失效保护
fail-
safe
单一故障准则
single-failure criterion
共因故障
common cause
failure
固有安全性
inherent safety
非能动安全
passive
safety
冗余性
redundancy
多样性
diversity
多层屏障
multiple barrier
纵深防御
defense in
depth
工作不正常,故障
malfunction
失效
failure
假设始发事件
postulated initiating
events
事故工况
accident condition
严重事故
severe accident
事故处理
accident management
设计基准事故
design basis accident
负荷丧失事故
loss
of
electrical
load
潜热
latent heat
accident
焓,热函
sensible heat, enthalpy
主
给
水丧
失事
故
loss
of
main
定期安全检查
periodic
safety inspection
water
accident
许可证
license
卡棒事故
stuck rod accident
监管
regulation
弹棒事故
rod ejection
accident
核安全准则
nuclear safety criteria
堵管裕量
tube
plugging margin
三
哩
岛
事
故
Three
Mile
Island
(TMI)
管道甩摆限制
pipe whip restraint
accident
在役检查
inservice
inspection
切尔诺贝利事故
Chernobyl accident
承压热冲击
pressurized
thermal shock
1.8.
放射性与辐射防护
radioactivity
放射性
shielding
屏蔽
scatter
散射
biological
shield
生物屏蔽
deflect,
deflection
折射
剂量
dose
衍射
diffraction
dose
equivalent
剂量当量
穿透
penetrate,
penetration
collective
dose
集体剂量
交互作用
interact,
interaction
individual
dose
个人剂量
ionization
电离
ingest,
ingestion
摄入,摄取
湮灭
annihilate
(v.), annihilation (n.)
inhale,
inhalation
吸入
衰减
attenuate(v.),
attenuation(n.)
coma
昏迷
projectile
入射离子
cramp
绞痛
radiation
protection
辐射防护
diarrhea
腹泻
radiation,
ray
辐射,射线
tremor
颤抖
< br>irradiation
辐照,
(向外)辐射
vomit
呕吐
internal
exposure
内照射
somatic
身体的
external
exposure
外照射
somatic
effect
躯体反应
occupational
dose
职业照射(剂量)
radiation
sickness
辐照病变
fluence
注量
symptom
征兆
cosmic ray
宇宙射线
therapy
治疗
x-ray X
射线
survivor
幸存者
?
/
?
/
?
射线
?
/
?
/
?
ray
activation
product
活化产物
health
physics
保健物理
effluent
废水
6
feed
natural
background
天然本底
sivert
希弗
spectrum
谱
雷姆
rem
氡
radon
as low as reasonably
achievable (ALARA)
合
理可行尽量低
radioactive waste
disposal
放射性废物处理
high-level (radioactive)
waste
高放废物
low-
level (radioactive)
waste
低放废物
1.9.
有关机构
International Atomic Energy Agency
(IAEA)
国际原子能机构
American Society of Mechanical
Engineers (ASME)
美国机械工程师学会
Nuclear Regulatory Commission
(NRC/USNRC)
美国核管会
Department Of Energy (DOE)
美国能源部
World
Association of Nuclear Operators (W
ANO)
世界核电运营者协会
International Commission on
Radiological Protection (ICRP)
国际辐射防护委员会
China
Atomic Energy Authority
(
CAE
A
)中国国家原子能机构
State
Environment Protection Administration of
China
国家环保总局
1.10.
其它术语
1.10.1.
表示方向
lateral
横向
longitudinal
纵向
radial
径向
perpendicular
to
垂直于
vertically
mounted
垂直
/
立式安装
circumferential
环向
axial
轴向
periphery
周边
1.10.2.
材料失效术语
corrosion
腐蚀
stress corrosion
cracking
应力腐蚀开裂
rapture, fracture,
break
断裂
breach
破口
肿胀
swelling
cavitation
气蚀
pitting
点蚀
/
孔蚀
crevice
corrosion
缝隙腐蚀
erosion
冲蚀
FAC
flow
accelerated
corrosion
流动加速腐
蚀
wastage
耗蚀
(SG tube)
dent
凹陷,凹痕
fatigue
疲劳
ageing
老化
7
degradation
降级
wear
磨损
fretting wear
微动磨损
creep
蠕变
stress
应力
strain
应变
creep
strength
蠕变强度
tensile
strength
抗拉强度
yield
strength
屈服强度
rapture
strength
断裂强度
nil-
ductility
transition
tempera
ture
零延性转
变温度
thermal
stress
热应力
irradiation
swelling
辐照肿胀
deposit welding, overlaying, build-up
welding,
surface
welding
堆焊
seal
weld
密封焊
heat
affected zone (HAZ)
焊接热影响区
1.10.3.
核电工程术语
procurement
征购
site
厂址
call for bid, call for
tender
招标
commercial
offer
商务标
technical
offer
技术标
commencement
开工
contract
合同
firm
contract
不可更改的合同
subcontract
分包合同
commitment
承诺,任务
job site
工地,工作现场
technical requirement
技术要求
技术规格
technical
specification
non-
conformance
不符合项
delivery
交货
warehouse
仓库
construction
schedule
施工计划
Free
on Board (FOB)
离岸价格
Cost Insurance and Freight (CIF)
到岸价格
Engineering,
Procurement
&
Construction
EPC
合
同
-
设计采购建造
power grid
电网
distribution
system
输变电系统
1.10.4.
其它
compound
化合物
mixture
混合物
mass
质量
momentum
动量
energy
能量
potential (energy)
势能
kinetic
energy
动能
inertia
惯性
half-life
半衰期
mean free
path
平均自由程
fuel
cycle
燃料循环
hot
spot
热点
hot-
channel factor
热管因子
departure from nucleate boiling ratio
(DNBR)
偏离泡核沸腾比
heat transfer
传热
heat exchanger
换热器
heat conduction
导热
convection
对流
热辐射
thermal /
heat radiation
干度
quality
蒸汽
steam
预
应
力
钢
筋混
凝
土
prestressed
reinforced
8
concrete / prestressed concrete
钢筋混凝土
reinforced
concrete
铁钢沙混凝土
Steel shot concret
筋,钢筋束
tendon
流量分配
flow
distribution
电网
power grid
业主
utility
承包商
contractor
分包商
sub-contractor
压降
pressure drop
压差
differential pressure
水位
(water) level
规定,条款;保障;装备
provision
地震
earthquake
地震的
seismic
飓风
tornado
暖
通
空
调
Heating,
V
entilation
and
Air
Conditioning
(HV
AC)
热阱
heat sink
惰转
coastdown
惰转流量
coastdown flow
功率失常激增,功率漂移
power excursion
减轻,缓解
v.
mitigate, n. mitigation
公差、容差
allowance
间隙,公差
clearance
权重因子
weighting factor
1.11.
有必要了解的词汇与短语
as a
rule of thumb
根据经验
by orders of
magnitude
以数量级
incipient
failure
早期故障
,
初期故障
eliminate,
elimination
消除
derive, derivation, deduce, deduction
p>
导出,
起
源
mechanism, approach, principle,
theory
机理,
原理
susceptible
敏感的
susceptibility
敏感性
toxic
有毒的
acute
急剧的
inherit
遗传
hereditary
遗传性的
altitude
高度
postulate,
postulation
假定,假设
permeable
可渗透的
,
有渗透性的
impermeable
不可渗透的
brittle
fracture
脆性破裂
embrittlement
脆化
toughness
韧性
ductility
延展性
第
2
章
阅读理解题练习
2.1. Passage 1
As a result
reactor
designers have paid great
attention to the inherent safety
of
reactors
which
can
be
achieved
by
negative
temperature
and
power
coefficients
and
fail-safe
control
systems.
It
can
be
said
with
some
confidence
that present-day
thermal reactors are safe in the sense that under
no conceivable
circumstance
can
they
explode
like
a
bomb,
and
control
systems
have
been
designed which can, in the event of any
malfunction on the part of the reactor or
its associated plant, automatically and
rapidly shut down the reactor
, i.e.
make it
subcritical by a substantial
amount, in a very few seconds.
1.
According
to
the
paragraph,
inherent
safety
of
reactors
can
be
achieved
by
.
(
C
)
A. the operators;
B.
positive temperature and positive power
coefficients;
C. negative temperature
and negative power coefficients;
D.
passive safety system and positive power
coefficients.
2. The best
title of the passage may probably be
.
(
D
)
9
A. fail-safe
control system
;
B. thermal reactor safety and
operation;
C. automatic protective
system;
D. inherent safety design of
reactors.
2.2. Passage II
The biological shield should contain
some hydrogen compound to slow down
fast
neutrons,
and
be
dense
enough
to
attenuate
gamma
radiation
effectively.
Concrete satisfies both these
requirements fairly well and is suitable for
landbase
reactors.
Barytes
(
重晶石
)
concrete,
containing
the
heavy
element
barium,
and
steel-shot
concrete
have
been
used
for
biological
shields.
They
are
more
dense
than
ordinary
concrete,
with
improved
shielding
properties,
however
their
higher
cost
offsets
this
advantage.
The
biological
shield
for
a
marine
reactor
,
which
is
usually
a
fairly
compact
pressurized
water
reactor
,
must
satisfy
a
minimum
space
and
weight
requirement.
This
leads
to
a
shield
design
which
consists typically of
alternate layers of
water (for fast
neutron slowing) and steel
(for gamma ray attenuation).
3.
According
to
the
above
passage,
is
not
possible
for
constructing biological shield?
(
C
)
A. steel;
B. concrete;
C. graphite;
D. paraffin wax.
4. Which of the following
sentences is not true?
(
D
)
A.
The biological shield is
designed
mainly to slow
down
fast
neutrons and
attenuate gamma
radiation.
B. The marine reactor uses
alternative steel and water layers as its
biological
shield.
C. The
combination of heavy element concrete and steel
bars could improve
the shielding
properties.
D.
The
biological
shield
should
use
hydrogen
element
to
slow
down
fast
neutron and attenuate
gamma radiations.
2.3.
Passage III
In
order
to
mitigate
the
effects
of
large
release
of
steam
(an
potentially
of
radioactivity)
in
the
containment,
two
full
capacity
independent
safety
systems
10